10122 Federal Register / Vol. 60, No. 36 / Thursday, February 23, 1995 / Notices

underdose and the patient returned on

August 2, 1994, for the completion of

the therapy. The patient was given a

written report of the misadministration

on August 9, 1994. The licensee

submitted a report for the

misadministration on August 10, 1994.

NRC Region I has enlisted the services

of a medical consultant to evaluate the

clinical consequences of this

misadministration and awaits his report.

A copy of NUREG–0090, Vol. 17, No.

3 is available for inspection or copying

for a fee at the NRC Public Document

Room, 2120 L Street NW. (Lower Level),

Washington, D.C. 20037, or at any of the

nuclear power plant Local Public

Document Rooms throughout the

country.

Copies of this report (or any of the

previous reports in this series), may be

purchased from the Superintendent of

Documents, U.S. Government Printing

Office, Post Office Box 37082,

Washington, DC 20013–7082. A year’s

subscription to the NUREG–0090 series

publication, which consists of four

issues, is also available.

Copies of the report may also be

purchased from the National Technical

Information Service, U.S. Department of

Commerce, 5285 Port Royal Road,

Springfield, VA 22161.

Dated at Rockville, MD this 16th day of

February, 1995.

For the Nuclear Regulatory Commission.

John C. Hoyle,

Acting Secretary of the Commission.

[FR Doc. 95–4382 Filed 2–22–95; 8:45 am]

BILLING CODE 7590–01–M

[Docket Nos. 50–352 and 50–353]

In the Matter of: Philadelphia Electric

Company (Limerick Generating

Station, Units 1 and 2); Exemption

I.

Philadelphia Electric Company (the

licensee), is the holder of Facility

Operating License Nos. NPF–39 and

NPF–85, which authorize operation of

the Limerick Generating Station (LGS),

Units 1 and 2. The licenses provide,

among other things, that the licensee is

subject to all rules, regulations, and

orders of the Nuclear Regulatory

Commission (the Commission) now and

hereafter in effect. The facilities consist

of two boiling water reactors located in

Montgomery County, Pennsylvania.

II

Section 50.54(o) of 10 CFR Part 50

requires that primary reactor

containments for water cooled power

reactors be subject to the requirements

of Appendix J to 10 CFR Part 50.

Appendix J contains the leakage test

requirements, schedules, and

acceptance criteria for tests of the leak

tight integrity of the primary reactor

containment and systems and

components which penetrate the

containment. Sections II.H.4 and III.C.2

of Appendix J to 10 CFR Part 50 require

leak rate testing of Main Steam Isolation

Valves (MSIVs) at the calculated peak

containment pressure related to the

design basis accident, and Section

III.C.3 requires that the measured leak

rates be included in the combined local

leak rate test results. The proposed

deletion of the MSIV Leakage Control

System (LCS), and proposed use of an

alternate leakage pathway affects the

description of an existing exemption

which allows the leak rate testing of the

MSIVs at a reduced pressure and the

exclusion of the measured leakage from

the combined local leak rate test results.

The original exemption is contained in

the LGS Safety Evaluation Report (SER)

(NUREG–0991, and its Supplement 3).

By letter dated December 22, 1994,

the licensee requested an exemption

from the Commission’s regulations. The

subject exemption is from the

requirements of 10 CFR Part 50,

Appendix J, ‘‘Primary Reactor

Containment Leakage Testing for WaterCooled Power Reactors,’’ Sections II.H.4,

III.C.2, and III.C.3, to allow alternative

testing pressure and leakage limits for

the MSIVs and to exclude MSIV leakage

from the combined local leak rate test

results after deletion of the LCS.

The staff issued for LGS, Units 1 and

2, the current exemption from 10 CFR

Part 50, Appendix J, Sections II.H.4,

III.C.2, and III.C.3, based on the

conclusion that the LGS, Units 1 and 2,

MSIV leak testing methods were

acceptable alternatives to the

requirements. This conclusion was

included in the LGS SER (NUREG–0991,

and its Supplement 3). The SER also

described that in the event of a loss-ofcoolant-accident (LOCA), the MSIV LCS

will maintain a negative pressure

between the MSIV and the effluent will

be discharged into a volume where it

will be processed by the standby gas

treatment system before being released

to the environment. The licensee had

performed a radiological analysis based

on an assumed leak rate limit of 11.5

standard cubic feet per hour (scfh), and

the MSIVs were planned to be

periodically tested to ensure the validity

of the radiological analysis. The staff

concluded that the current LGS testing

procedure, where two valves on one

steam line are tested simultaneously,

between the valves, utilizing a reduced

test pressure (i.e., half a peak

containment pressure of 22 psig applied

between the MSIVs) was acceptable.

Also, the staff excluded the MSIV test

leakage rate from the combined local

leak rate because the MSIV leakage had

been accounted for separately in the

radiological analysis of the site.

By letter dated January 14, 1994, the

licensee submitted a Technical

Specifications (TS) amendment request

for LGS, Units 1 and 2, which supports

the planned modification to eliminate

the MSIV LCS and utilize an alternate

leakage pathway (main steam lines and

condenser). This proposal is based on

the Boiling Water Reactor Owners

Group (BWROG) method summarized in

General Electric Report NEDC–31858P,

Revision 2, ‘‘BWROG Report for

increasing MSIV Leakage Rate Limits

and Elimination of Leakage Control

System.’’ Therefore, the description of

the MSIV LCS and the assumed MSIV

leak rate are no longer accurate once the

proposed TS modification is performed

and implemented.

The licensee’s January 14, 1994, TS

(amendment) request states that a plantspecific radiological analysis has been

performed in accordance with NEDC–

31858P, Revision 2, to assess the effects

of the proposed increase to the

allowable MSIV leakage rate in terms of

Main Control Room (MCR) and off-site

doses following a postulated design

basis LOCA. This analysis utilizes the

hold-up volume of the main steam

piping and condenser as an alternate

method for treating MSIV leakage. The

radiological analysis uses standard

conservative assumptions for the

radiological source term consistent with

Regulatory Guide (RG) 1.3,

‘‘Assumptions Used for Evaluating the

Potential Radiological Consequences of

a Loss-of-Coolant-Accident for Boiling

Water Reactors,’’ Revision 2, dated June

1974. The analysis results demonstrate

that dose contributions from the

proposed MSIV leakage rate limit of 100

scfh per MSIV, not to exceed 200 scfh

for all four main steam lines, and

considering the proposed deletion of the

MSIV LCS, result in an acceptable

increase to the LOCA doses previously

evaluated against the regulatory limits

for the off-site doses and MCR doses

contained in 10 CFR Part 100, and 10

CFR Part 40, Appendix A, General

Design Criteria (GDC) 19, respectively.

The proposed calculated off-site and

MCR doses resulting from a LOCA are

the sum of the LOCA doses previously

evaluated (currently described in the

Updated Final Safety Analysis Report),

and the additional doses calculated

using the alternate MSIV leakage

treatment method. The method of

calculating the revised doses is

conservative, since the LOCA doses
Federal Register / Vol. 60, No. 36 / Thursday, February 23, 1995 / Notices 10123

previously evaluated already include

dose contributions from MSIV leakage at

the maximum leakage rate currently

permitted by the TS. Appendix 2 of

Attachment 3 of the January 14, 1994,

submittal shows the previously

calculated doses and the new calculated

doses resulting from the proposed

changes.

The staff concluded that the current

exemption was acceptable based on:

The method of MSIV testing (i.e., 22

psig test pressure when applied between

MSIVs on a single steam line); a

radiological analysis that assumed a

11.5 scfh MSIV leak rate, and the

licensee’s commitment that the MSIVs

would be periodically tested to ensure

the validity of the radiological analysis

(i.e., verify that the MSIV leakage rate

during testing is accounted for

separately in the radiological analysis of

the site. The proposed changes do not

affect the bases for the current

exemption. The modification and

implementing TS change request: Will

not alter the procedure method of MSIV

testing (i.e., test pressure will remain at

22 psig when applied between MSIVs)

and are based on the results of a

radiological analysis where the

proposed leakage rate and the resulting

doses are still within regulatory limits.

Also, the MSIVs will be periodically

tested to assure the validity of the

analysis (i.e., verify that the proposed

MSIV leakage rate assumed in the

radiological analysis is not exceeded per

proposed TS 3.6.1.2.c), and the MSIV

leakage will still be accounted for

separately in the radiological analysis of

the site.

For the reasons set forth above, the

NRC staff concludes that there is

reasonable assurance that: The current

MSIV leak testing method (i.e., test

pressure of 22 psig when applied

between MSIV) is an acceptable method;

the proposed alternate MSIV leakage

pathway (main steam lines and

condenser), and the calculated doses

obtained by performing radiological

analysis (calculated using an MSIV

leakage rate limit of 100 scfh per MSIV

not to exceed 200 scfh for all four main

steam lines) are within the limits of 10

CFR Part 100 and GDC 19. The staff

finds it acceptable to continue to

exclude the measured MSIV leakage rate

from the combined local rate, since the

leakage is accounted for separately and

continues to meet the underlying

purpose of the rule. Therefore, the staff

finds the requested exemption

presented in the licensee’s December 22,

1994, submittal acceptable.

III

Pursuant to 10 CFR 50.12, the

Commission may, upon application by

any interested person or upon its own

initiative, grant exemptions from the

requirements of 10 CFR Part 50 when (1)

the exemptions are authorized by law,

will not present an undue risk to public

health and safety, and are consistent

with the common defense and security;

and (2) when special circumstances are

present. Special circumstances are

present whenever, according to 10 CFR

50.12(a)(2)(ii), ‘‘Application of the

regulation in the particular

circumstances would not serve the

underlying purpose of the rule or is not

necessary to achieve the underlying

purpose of the rule * * *,’’

The underlying purpose of the rule is

to assure that the total valve leakage is

within the limits of 10 CFR Part 100 and

GDC–19. The licensee’s analysis has

demonstrated that an adequate margin

can be maintained even if leakage from

the MSIV is considered separately and

subject to a leakage restriction of 100

scfh per MSIV, not to exceed a total of

200 scfh for all four main steam lines.

IV

Accordingly, the Commission has

determined that, pursuant to 10 CFR

Part 50.12, an exemption is authorized

by law and will not present an undue

risk to the public health and safety, and

that there are special circumstances

present, as specified in 10 CFR

50.12(a)(2). An exemption is hereby

granted from the requirements of

Sections II.H.4, III.C.2(a), and III.C.3 of

Appendix J to 10 CFR Part 50. The

exemption allows (1) leakage testing of

the MSIVs after deletion of the LCS,

using a test pressure of 22 psig applied

between MSIVs and a leakage rate limit

of 100 scfh per MSIV, not to exceed 200

scfh for all main steam lines, and (2)

exclusion of the measured MSIV leakage

rate from the combined local leak rate.

Pursuant to 10 CFR 51.32, the

Commission has determined that the

granting of this exemption will have no

significant impact on the quality of the

human environment (60 FR 7226).

The exemption is effective upon

issuance and will be implemented prior

to startup of Cycle 4 for LGS, Unit 2,

and prior to startup of Cycle 7 for LGS,

Unit 1.

Dated at Rockville, Maryland this 16th day

of February 1995.

[FR Doc. 95–4383 Filed 2–22–95; 8:45 am]

BILLING CODE 7590–01–M

[Docket No. 50–353]

Philadelphia Electric Company; Notice

of Issuance of Amendment to Facility

Operating License

The U.S. Nuclear Regulatory

Commission (Commission) has issued

Amendment No. 53 to Facility

Operating License No. NPF–85 issued to

Philadelphia Electric Company, which

revised the Technical Specifications for

operation of the Limerick Generating

Station, Unit 2, located in Montgomery

County, Pennsylvania.

The amendment is effective as of the

date of issuance. The amendment

modified the Technical Specifications to

permit an increase in the allowable leak

rate for main steam isolation valves

(MSIV), and delete the MSIV leakage

control system (LCS). The main steam

drain lines and the main condenser

would be utilized as an alternate MSIV

leakage treatment system.

The application for the amendments

complies with the standards and

requirements of the Atomic Energy Act

of 1954, as amended (the Act), and the

Commission’s rules and regulations.

The Commission has made appropriate

findings as required by the Act and the

Commission’s rules and regulations in

10 CFR Chapter I, which set forth in the

license amendment.

Notice of Consideration of Issuance of

Amendments and Opportunity for

Hearing in connection with this action

was published in the Federal Register

on September 26, 1994 (59 FR 49089).

No request for a hearing or petition for

leave to intervene was filed following

this notice.

The Commission has prepared an

Environmental Assessment related to

the action and has determined not to

prepare an environmental impact

statement. Based upon the

environmental assessment, the

Commission has concluded that the

issuance of the amendment will not

have a significant effect on the quality

of the human environment (60 FR 7226).

For further details with respect to the

action see (1) the application for

amendments dated January 14, 1994,

and supplemented by letters dated

August 1, October 25, December 13,

December 22, 1994 (two submittals),

and February 7, 1995 (2) Amendment

No. 53 to License No. NPF–85, (3) the

Commission’s related Safety Evaluation,

and (4) the Commission’s

Environmental Assessment. All of these

items are available for public inspection

at the Commission’s Public Document

Room, the Gelman Building, 2120 L

Street NW., Washington, DC, and at the

local public document room located at