[Federal Register Volume 69, Number 188 (Wednesday, September 29, 2004)]
[Notices]
[Pages 58205-58208]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 04-21765]


-----------------------------------------------------------------------

NUCLEAR REGULATORY COMMISSION

[Docket Nos. 50-315 and 50-316]


Indiana Michigan Power Company; Notice of Consideration of 
Issuance of Amendments To Facility Operating Licenses and Opportunity 
for a Hearing

    The U.S. Nuclear Regulatory Commission (NRC or the Commission) is 
considering issuance of an amendment to Facility Operating License Nos. 
DPR-58 and DPR-74 issued to Indiana Michigan Power Company (I&M or the 
licensee) for operation of the Donald C. Cook Nuclear Plant, Units 1 
and 2, (D. C. Cook) located in Berrien County, Michigan.
    The proposed amendment, requested by I&M in its application dated 
April 6, 2004, represents a full conversion from the Current Technical 
Specifications (CTS) to a set of Improved Technical Specifications 
(ITS) based on NUREG-1431, ``Standard Technical Specifications (STS) 
for Westinghouse Plants,'' Revision 2, dated April 2001. NUREG-1431 has 
been developed by the Commission's staff through working groups 
composed of both NRC staff members and industry representatives, and 
has been endorsed by the NRC staff as part of an industry-wide 
initiative to standardize and improve the Technical Specifications 
(TSs) for nuclear power plants. As part of this submittal, the licensee 
has applied the criteria contained in the Commission's ``Final Policy 
Statement on Technical Specification Improvements for Nuclear Power 
Reactors (Final Policy Statement),'' published in the Federal Register 
on July 22,1993 (58 FR 39132), to the CTS and using NUREG-1431 as a 
basis, proposed an ITS for D. C. Cook. The criteria in the Final Policy 
Statement was subsequently added to Title 10 of the Code of Federal 
Regulations (10 CFR), Part 50.36, ``Technical Specifications,'' in a 
rule change that was published in the Federal Register on July 19, 1995 
(60 FR 36953) and became effective on August 18, 1995.
    In addition to the conversion, the licensee also proposed: (1) To 
delete three license conditions in the operating licenses for D. C. 
Cook Units 1 and 2 and relocate the requirements to either the ITS or 
the Technical Requirements Manual of the D. C. Cook Updated Final 
Safety Analysis Report (UFSAR); and (2) 34 beyond scope issues (BSIs) 
where the proposed requirements are different from the CTS or the STS 
NUREG-1431. The BSIs are identified later in this notice.
    This notice is based on the application dated April 6, 2004, and 
the information provided to the NRC through the Cook ITS Conversion Web 
page. To expedite its review of the application, the NRC staff issued 
its requests for additional information (RAIs) through the Cook ITS 
Conversion Web page and the licensee addressed the RAIs by providing 
responses on the Web page. Entry into the database is protected so that 
only licensee and NRC reviewers can enter information into the database 
to add RAIs (NRC) or providing responses to the RAIs (licensee); 
however, the public can enter the database to only read the questions 
asked and the responses provided. To be in compliance with the 
regulations for written communications for license amendment requests 
and to have the database on the D. C. Cook dockets before the 
amendments would be issued, the licensee will submit a copy of the 
database in a submittal to the NRC after there are no further RAIs and 
before the amendments would be issued. The public can access the 
database through the NRC Web site at http://www.nrc.gov by the 
following process: (1) Click on the tab labeled ``Nuclear Reactors'' on 
the NRC home page along the upper part of the web page, (2) then click 
on the link to ``Operating Reactors,'' which is under ``Regulated 
Activities'' on the left hand side of the web page, (3) then click on 
the link to ``Improved Standard Technical Specifications'' which is on 
right hand side of the page, and (4) finally click on the link to 
``Comments on the application and responses by D. C. Cook,'' near the 
bottom of the Web page, to open the database. The RAIs and responses to 
RAIs are organized by ITS Sections 1.0, 2.0, 3.0, 3.1 through 3.9, 4.0, 
and 5.0, which are listed first, and the 34 BSIs, which are listed 
later. For every listed ITS section or BSI, there is an RAI which can 
be read by clicking on the ITS section or BSI number. The licensee's 
responses are shown by a solid triangle adjacent to the ITS section or 
BSI number, and, to read the response, you click on the triangle. To 
page down through the ITS sections to the BSIs, click on ``next'' along 
the top of the page or on ``previous'' to return to the previous page.
    The licensee has categorized the proposed changes to the CTS into 
five general groupings within the description of changes (DOC) section 
of the application. These groupings are characterized as administrative 
changes (i.e., ITS x.x, DOC A.xx), more restrictive changes (i.e., ITS 
x.x, DOC M.xx), relocated specifications (i.e., ITS x.x, DOC R.xx), 
removed detail changes (i.e., ITS x.x, DOC LA.xx), and less restrictive 
changes (i.e., ITS x.x, DOC L.xx). This is to say that the DOCs are 
numbered sequentially within each letter designator for each ITS 
Chapter, Section, or Specification, and the designations are A.xx for 
administrative changes, M.xx for more restrictive changes, R.xx for 
relocated specifications, LA.xx for removed detail changes, and L.xx 
for less restrictive changes. These changes to the requirements of the 
CTS do not result in operations that will alter assumptions relative to 
mitigation of an analyzed accident or transient event.
    Administrative changes are those that involve restructuring, 
renumbering, rewording interpretation and complex rearranging of 
requirements and other changes not affecting technical content or 
substantially revising an operating requirement. The reformatting, 
renumbering and rewording process reflects the attributes of NUREG-1431 
and does not involve technical changes to the CTS. The proposed changes 
include: (a) Providing the appropriate numbers, etc., for NUREG-1431 
bracketed information (information that must be supplied on a plant-
specific basis, and which may change from plant to plant); (b) 
identifying plant-specific wording for system names, etc.; and (c) 
changing NUREG-1431 section wording to conform to existing licensee 
practices. Such changes are administrative in nature and do not impact 
initiators of analyzed events or assumed mitigation of accident or 
transient events. [FEDREG][VOL]*[/VOL][NO]*[/NO][DATE]*[/
DATE][NOTICES][NOTICE][PREAMB][AGENCY]*[/AGENCY][SUBJECT]*[/SUBJECT]
    More restrictive changes are those involving more stringent 
requirements compared to the CTS for operation of the facility. These 
more stringent requirements do not result in operation that will alter 
assumptions relative to the mitigation of an accident or transient 
event. The more restrictive requirements will not alter the operation 
of process variables, structures, systems, and components described in 
the safety analyses. For each requirement in the STS that is more 
restrictive than the CTS that the licensee proposes to adopt in the 
ITS, the licensee has provided an explanation as to why it has 
concluded

[[Page 58206]]

that adopting the more restrictive requirement is desirable to ensure 
safe operation of the facility because of specific design features of 
the plant.
    Relocated changes are those involving relocation of requirements 
and surveillances for structures, systems, components, or variables 
that do not meet the criteria for inclusion in TSs. Relocated changes 
are those CTS requirements that do not satisfy or fall within any of 
the four criteria specified in the 10 CFR 50.36(c) and, therefore, may 
be relocated to appropriate licensee-controlled documents.
    The licensee's application of the screening criteria is described 
in Attachment 1 to the licensee's April 6, 2004, application, ``Donald 
C. Cook Nuclear Plant, Units 1 and 2, License Amendment Request--
Conversion of Current Technical Specifications (CTS) to Improved 
Technical Specifications (ITS).'' The affected structures, systems, 
components or variables are not assumed to be initiators of analyzed 
events and are not assumed to mitigate accident or transient events. 
The requirements and surveillances for these affected structures, 
systems, components, or variables will be relocated from the TSs to 
administratively-controlled documents such as the quality assurance 
program, the UFSAR, the ITS Bases, the technical requirements manual 
that is incorporated by reference in the UFSAR, the core operating 
limits report, the offsite dose calculation manual, the inservice 
testing program, the inservice inspection program, or other licensee-
controlled documents. Changes made to these documents will be made 
pursuant to 10 CFR 50.59 or other appropriate control mechanisms, and 
may be made without prior NRC review and approval. In addition, the 
affected structures, systems, components, or variables are addressed in 
existing surveillance procedures that are also subject to 10 CFR 50.59.
    Removed detail changes, are changes to the CTS that eliminate 
detail and relocate the detail to a licensee-controlled document. 
Typically, this involves details of system design and function, or 
procedural detail on methods of conducting a surveillance requirement 
(SR). These changes are supported, in aggregate, by a single generic no 
significant hazard consideration. The generic type of removed detail 
change is identified in italics at the beginning of the DOC.
    Less restrictive changes are those where CTS requirements are 
relaxed or eliminated, or new plant operational flexibility is 
provided. The more significant ``less restrictive'' requirements are 
justified on a case-by-case basis. When requirements have been shown to 
provide little or no safety benefit, their removal from the TSs may be 
appropriate. In most cases, relaxations previously granted to 
individual plants on a plant-specific basis were the result of: (a) 
Generic NRC actions; (b) new NRC staff positions that have evolved from 
technological advancements and operating experience; or (c) resolution 
of the Owners Groups' comments on the Improved STSs. Generic 
relaxations contained in NUREG-1431 were reviewed by the NRC staff and 
found to be acceptable because they are consistent with current 
licensing practices and NRC regulations. The licensee's design is being 
reviewed to determine if the specific design basis and licensing basis 
are consistent with the technical basis for the model requirements in 
NUREG-1431, thus providing a basis for the ITS, or if relaxation of the 
requirements in the CTS is warranted based on the justification 
provided by the licensee.
    These administrative, relocated, more restrictive, and less 
restrictive changes to the requirements of the CTS do not result in 
operations that will alter assumptions relative to mitigation of an 
analyzed accident or transient event.
    In addition to the proposed changes solely involving the 
conversion, there are also changes proposed that are different from the 
requirements in both the CTS and the STS NUREG-1431. The BSIs are 
listed below in which the first 21 were identified by the licensee and 
addressed in Enclosure 4 to its application. In some cases, the BSI is 
addressed as a justification for deviation (JFD) from the STS, and 
identified as ITS x.x, JFD x. These BSIs to the conversion, listed in 
the order of the applicable ITS specification or section, are as 
follows [note that the words below that are capitalized are terms that 
are defined in the ITS]:
    (1) Surveillance Frequencies for certain CHANNEL CALIBRATION 
Surveillance Requirements (SRs) are being changed from 18 months in the 
CTS to either 31 days or 184 days in the ITS. (ITS 3.3.1, DOC M.16; ITS 
3.3.2, DOC M.10; ITS 3.3.5, DOC M.2)
    (2) Changing certain ALLOWABLE VALUES as a result of extending the 
CHANNEL CALIBRATION surveillance frequency from 18 months to 24 months. 
(ITS 3.3.1, DOC M.17; ITS 3.3.1, DOC L.19; ITS 3.3.2, DOC M.11; ITS 
3.3.2, DOC L.22
    (3) Certain surveillance frequencies are being changed from 7 days, 
31 days, or 92 days to 184 days. (ITS 3.3.1, DOC L.18; ITS 3.3.2, DOC 
L.19; ITS 3.3.5, DOC L.5; ITS 3.3.6, DOC L.9; ITS 3.4.15, DOC L.8; ITS 
3.6.9, DOC L.3; ITS 3.7.10, DOC L.3; ITS 3.7.12, DOC L.3; ITS 3.7.13, 
DOC L.5)
    (4) Decreases the number of manual channels required OPERABLE to 
one per train. (ITS 3.3.2, DOC L.20)
    (5) Decreases the number of manual channels required OPERABLE to 
one per train. (ITS 3.3.6, DOC L.10)
    (6) Deletes the once per shift SOURCE CHECK requirement on the 
containment radiation instrumentation. (ITS 3.3.6, DOC L.11)
    (7) Changes the number coolant loop required to be in operation 
and/or OPERABLE, based on the status of the rod control system. (ITS 
3.4.6, DOC L.1)
    (8) Requirement to specifically state the required water level as 
referenced to a specific point inside the steam generators instead of 
using a specific indication from one instrument is being changed. (ITS 
3.4.6, DOC L.5; ITS 3.4.7, DOC L.3)
    (9) Changes for Unit 1 only to: (1) Decrease the unidentified 
LEAKAGE limit and provide additional REQUIRED ACTIONS; and (2) add the 
requirement to analyze grab samples of the containment atmosphere every 
12 hours instead of every 24 hours. (ITS 3.4.13, DOC M.1; ITS 3.4.15, 
DOC M.2)
    (10) Increasing the pressure constant value, resulting in a 
decrease in the calculated seal line resistance flow. (ITS 3.5.5, DOC 
M.1)
    (11) Require two of the three refueling canal drains to be 
OPERABLE, and, due to this change, the word ``required'' has been added 
to the Actions and the SRs since not all installed refueling drains are 
required to be OPERABLE. (ITS 3.6.14, DOC L.2)
    (12) Increasing the condensate storage tank volume requirements. 
(ITS 3.7.6, DOC M.1)
    (13) Delete the 1-hour allowance to delay declaring inoperable the 
opposite unit essential service water (ESW) train, and adds 
requirements to address the opposite unit ESW train. (ITS 3.7.8, DOC 
M.3)
    (14) Ensure only one control room air conditioning (CRAC) train is 
in operation and change the temperature limit from 95 [deg]F to 85 
[deg]F during the 12-hour surveillance, and add a specific requirement 
to verify that each CRAC train can maintain control room air 
temperature < 85 [deg]F every 31 days, and add requirements to verify 
control room air temperature. (ITS 3.7.11, DOC M.2)
    (15) Add the requirement that the required fuel handling area 
exhaust ventilation (FHAEV) train must be in operation, add an ACTION 
to take if the required FHAEV train is not in operation, add a new 
surveillance

[[Page 58207]]

requirement to periodically verify the required FHAEV train is in 
operation, and delete a surveillance requirement to verify the train 
automatically directs its exhaust flow through the charcoal adsorber 
banks on an actuation signal. (ITS 3.7.13, DOC M.1)
    (16) Reduce the steady-state voltage range from 4160 <plus-minus> 
420 V to 4160 +240 V, -250 V, and the steady-state frequency range from 
60 <plus-minus> 1.2 Hz to 60 + 1.2 Hz, -0.6 Hz. (ITS 3.8.1, DOC M.5)
    (17) Delete the requirement to perform the surveillance requirement 
in accordance with the Diesel Generator (DG) Test Schedule Table, and 
change the nominal test frequency to 92 days. (ITS 3.8.1, DOC L.19)
    (18) Deletes requirements in CTS SR 4.8.1.1.2.e.10 on testing the 
DG. (ITS 3.8.1, DOC L.20)
    (19) Changes the time to perform surveillance requirement checks 
from 8 hours or 24 hours, to 12 hours. (ITS 3.8.1, DOC L.21)
    (20) Certain CTS SRs are not required in the ITS. (ITS 3.8.2, DOC 
L.6)
    (21) Extend the surveillance frequency for various surveillance 
requirements to 24 months, consistent with the guidelines provided in 
NRC Generic Letter 91-04. (ITS 3.1.4, DOC L.9; ITS 3.3.1, DOCs L.1, 
L.2, L.3 and L.11; ITS 3.3.2, DOCs L.1, L.2, L.4 and L.13; ITS 3.3.3, 
DOC L.6; ITS 3.3.4, DOC L.1; ITS 3.3.6, DOCs L.5 and L.6; ITS 3.3.7, 
DOC L.2; ITS 3.3.8, DOC L.3; ITS 3.4.1, DOC L.2; ITS 3.4.9, DOC L.1; 
ITS 3.4.11, DOC L.3; ITS 3.4.12, DOC L.3; ITS 3.4.14, DOC L.4; ITS 
3.4.15, DOC L.6; ITS 3.5.2, DOC L.3; ITS 3.6.3, DOC L.5; ITS 3.6.6, DOC 
L.1; ITS 3.6.7, DOC L.1; ITS 3.6.8, DOC L.3; ITS 3.6.9, DOC L.2; ITS 
3.6.13, DOC L.1; ITS 3.7.5, DOC L.8; ITS 3.7.7, DOC L.2; ITS 3.7.8, DOC 
L.2; ITS 3.7.10, DOC L.2; ITS 3.7.12, L.2; ITS 3.7.13, DOC L.4; ITS 
3.8.1, DOC L.3; ITS 3.8.4, DOC L.2; and ITS 5.5, DOCs L.1 and L.3)
    (22) The surveillance frequency is changed from prior to reactor 
startup if not performed within the previous 7 days to 24 months. (ITS 
3.3.1, DOC L.12)
    (23) CTS Table 4.3-1 requires a CHANNEL CALIBRATION of Functional 
Units 7 and 8, the Overtemperature delta T and Overpower delta T 
channels, respectfully. The ITS specifies the normalization of the 
delta T channels is not required to be performed until 72 hours after 
Thermal Power is greater than or equal to 98 percent rated thermal 
power. (ITS 3.3.1, DOC M.10)
    (24) CTS Table 4.3-1 Functional Units 18.A and 18.B specify the SRs 
for the Turbine Trip--Low Fluid Oil Pressure and Turbine Stop Valve 
Closure Functions, but does not include a CHANNEL CALIBRATION 
requirement. ITS SR 3.3.1.13 has been added which requires a CHANNEL 
CALIBRATION of these channels every 24 months. (Table 3.3.1-1 Functions 
16.a and 16.b). (ITS 3.3.1, DOC M.14)
    (25) The CTS is being changed by adding the explicit Automatic 
Actuation Logic and Actuation Relays SRs for ITS Function 5.a, Turbine 
Trip and Feedwater Isolation. The frequency proposed for the slave 
relay (24 months) is consistent with the frequency proposed for the 
simulated actuation tests. (ITS 3.3.2, DOC M.2)
    (26) The proposed test frequencies are based on consistency with 
either other functions or with simulated actuation tests. (ITS 3.3.2, 
DOC M.3)
    (27) Licensee is applying WCAP-10271 to the Containment Air 
Recirculation Fan Actuation logic, and Containment Pressure--High 
Functions. (ITS 3.3.2, DOC L.5)
    (28) Licensee applying WCAP-10271, WCAP-15376 and WCAP-14333 for 
the required actions, completion times, and surveillance test intervals 
for the functions listed in DOC L.5 and L.17. (ITS 3.3.2, DOC L.5 and 
L.17)
    (29) Deviation from STS for the P-12 interlock action to place in 
``trip'' instead of ``place in the required state.'' (ITS 3.3.2, JFD 
23)
    (30) Eliminate requirements for residual heat removal trip bypass 
when the refueling water storage tank level instrumentation becomes 
inoperable. (ITS 3.3.3, DOC L.4)
    (31) Relax the CTS surveillance frequency for the hydrogen analyzer 
by deleting the requirement to test on a STAGGERED TEST BASIS. (ITS 
3.3.3, DOC L.13)
    (32) Adopt the STS repair allowed outage time of 6 hours before the 
channel must be placed in trip. (ITS 3.3.5, DOC L.2)
    (33) Add a setpoint methodology citation to the ITS Bases. (ITS 
3.3.5, Bases Insert 4--Reference 4)
    (34) Revise the wording in Required Action A.1 of ITS 3.5.5. (ITS 
3.5.5, JFD 4)
    Before issuance of the proposed license amendments, the Commission 
will have made findings required by the Atomic Energy Act of 1954, as 
amended (the Act) and the commission's regulations.
    Within 60 days after the date of publication of this notice, the 
licensee may file a request for a hearing with respect to issuance of 
the amendment to the subject facility operating license and any person 
whose interest may be affected by this proceeding and who wishes to 
participate as a party in the proceeding must file a written request 
for a hearing and a petition for leave to intervene. Requests for a 
hearing and a petition for leave to intervene shall be filed in 
accordance with the Commission's ``Rules of Practice for Domestic 
Licensing Proceedings'' in 10 CFR Part 2. Interested persons should 
consult a current copy of 10 CFR 2.309, which is available at the 
Commission's Public Document Room (PDR), located at One White Flint 
North, Public File Area 01F21, 11555 Rockville Pike (First Floor), 
Rockville, Maryland. Publicly available records will be accessible from 
the Agencywide Documents Access and Management System's (ADAMS) Public 
Electronic Reading Room on the Internet at the NRC Web site, [E 
T='03']http://www.nrc.gov/reading-rm/doc-collections/cfr/.[/E] If a 
request for a hearing or petition for leave to intervene is filed by 
the above date, the Commission or a presiding officer designated by the 
Commission or by the Chief Administrative Judge of the Atomic Safety 
and Licensing Board Panel, will rule on the request and/or petition; 
and the Secretary or the Chief Administrative Judge of the Atomic 
Safety and Licensing Board will issue a notice of a hearing or an 
appropriate order.
    As required by 10 CFR 2.309, a petition for leave to intervene 
shall set forth with particularity the interest of the petitioner/
requestor in the proceeding, and how that interest may be affected by 
the results of the proceeding. The petition should specifically explain 
the reasons why intervention should be permitted with particular 
reference to the following general requirements: (1) The name, address 
and telephone number of the requestor or petitioner; (2) the nature of 
the requestor's/petitioner's right under the Act to be made a party to 
the proceeding; (3) the nature and extent of the requestor's/
petitioner's property, financial, or other interest in the proceeding; 
and (4) the possible effect of any decision or order which may be 
entered in the proceeding on the requestor's/petitioner's interest. The 
petition must also identify the specific contentions which the 
petitioner/requestor seeks to have litigated at the proceeding.
    Each contention must consist of a specific statement of the issue 
of law or fact to be raised or controverted. In addition, the 
petitioner/requestor shall provide a brief explanation of the bases for 
the contention and a concise statement of the alleged facts or expert 
opinion which support the contention and on which the petitioner 
intends to rely in proving the contention at the

[[Page 58208]]

hearing. The petitioner must also provide references to those specific 
sources and documents of which the petitioner is aware and on which the 
petitioner intends to rely to establish those facts or expert opinion. 
The petition must include sufficient information to show that a genuine 
dispute exists with the applicant on a material issue of law or fact. 
Contentions shall be limited to matters within the scope of the 
amendment under consideration. The contention must be one which, if 
proven, would entitle the petitioner/requestor to relief. A petitioner/
requestor who fails to satisfy these requirements with respect to at 
least one contention will not be permitted to participate as a party.
    Those permitted to intervene become parties to the proceeding, 
subject to any limitations in the order granting leave to intervene, 
and have the opportunity to participate fully in the conduct of the 
hearing.
    Nontimely requests and/or petitions and contentions will not be 
entertained absent a determination by the Commission or the presiding 
officer of the Atomic Safety and Licensing Board that the petition, 
request and/or the contentions should be granted based on a balancing 
of the factors specified in 10 CFR 2.309(a)(1)(i)-(viii). ?>
    A request for a hearing or a petition for leave to intervene must 
be filed by: (1) First class mail addressed to the Office of the 
Secretary of the Commission, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001, Attention: Rulemaking and Adjudications 
Staff; (2) courier, express mail, and expedited delivery services: 
Office of the Secretary, Sixteenth Floor, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland, 20852, Attention: Rulemaking and 
Adjudications Staff; (3) e-mail addressed to the Office of the 
Secretary, U.S. Nuclear Regulatory Commission, <a href="/cdn-cgi/l/email-protection#db939e9a8992959c9f9498909e8f9b958998f59c948d"><span class="__cf_email__" data-cfemail="4b030e0a1902050c0f0408000e1f0b051908650c041d">[email protected]</span></a>; 
or (4) facsimile transmission addressed to the Office of the Secretary, 
U.S. Nuclear Regulatory Commission, Washington, DC, Attention: 
Rulemakings and Adjudications Staff at (301) 415-1101, verification 
number is (301) 415-1966. A copy of the request for hearing and 
petition for leave to intervene should also be sent to the Office of 
the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001, and it is requested that copies be transmitted either by 
means of facsimile transmission to (301) 415-3725 or by e-mail to 
<a href="/cdn-cgi/l/email-protection#155a525658747c7956707b617067557b67763b727a63"><span class="__cf_email__" data-cfemail="6b242c28260a0207280e051f0e192b051908450c041d">[email protected]</span></a>. A copy of the request for hearing and petition 
for leave to intervene should also be sent David W. Jenkins, Esq., 500 
Circle Drive, Buchanan, MI 49107, attorney for the licensee.
    For further details with respect to this action, see the licensee's 
application for amendment dated April 6, 2004, and the Cook ITS 
Conversion Web page (as discussed above). Documents may be examined, 
and/or copied for a fee at the Commission's PDR, located at One White 
Flint North, Public File Area O1 F21, 11555 Rockville Pike (First 
Floor), Rockville, Maryland. Publicly available records will be 
accessible electronically from the Agencywide Documents Access and 
Management System's (ADAMS) Public Electronic Reading Room on the 
Internet at the NRC Web site, http://www.nrc.gov/reading-rm/adams.html. 
Persons who do not have access to ADAMS or who encounter problems in 
accessing the documents located in ADAMS, should contact the NRC PDR 
Reference staff by telephone at 1-800-397-4209, (301) 415-4737, or by 
e-mail to <a href="/cdn-cgi/l/email-protection#c4b4a0b684aab6a7eaa3abb2"><span class="__cf_email__" data-cfemail="0a7a6e784a647869246d657c">[email protected]</span></a>.

    For the Nuclear Regulatory Commission.

    Dated at Rockville, Maryland, this 23rd day of September, 2004.
Jack Donohew,
Senior Project Manager, Section 2, Project Directorate IV, Division of 
Licensing Project Management, Office of Nuclear Reactor Regulation.
[FR Doc. 04-21765 Filed 9-28-04; 8:45 am]
BILLING CODE 7590-01-P


</pre><script data-cfasync="false" src="/cdn-cgi/scripts/5c5dd728/cloudflare-static/email-decode.min.js"></script></body>
</html>