Federal Register / Vol. 75, No. 101 / Wednesday, May 26, 2010 / Notices 29587 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2010–0185] 

Notice of Availability of Revised Model 

Proposed No Significant Hazards 

Consideration Determination for PlantSpecific Adoption of Technical 

Specifications Task Force Traveler 

TSTF–475, Revision 1, ‘‘Control Rod 

Notch Testing Frequency and SRM 

Insert Control Rod Action’’ 

AGENCY: Nuclear Regulatory 

Commission (NRC). 

ACTION: Notice of Availability. 

SUMMARY: The Notice of Availability 

(NOA) for adoption of TSTF–475, 

Revision 1, using the Consolidated Line 

Item Improvement Process (CLIIP), was 

published in the Federal Register on 

November 13, 2007 (72 FR 63935). The 

prior NOA followed the CLIIP and 

contained a model safety evaluation, a 

model license amendment application, 

and a model proposed no significant 

hazards consideration determination 

(NSHCD). The purpose of this NOA is 

to revise the model proposed NSHCD. 

Technical Specifications Task Force 

(TSTF) Traveler TSTF–475, Revision 1, 

‘‘Control Rod Notch Testing Frequency 

and SRM Insert Control Rod Action,’’ is 

available in the Agencywide Documents 

Access and Management System 

(ADAMS) under Accession Number 

ML071420428. 

Documents: You can access publicly 

available documents related to this 

notice using the following methods: 

NRC’s Public Document Room (PDR): 

The public may examine and for a fee 

have copied publicly available 

documents at the NRC’s PDR, Room O1 

F21, One White Flint North, 11555 

Rockville Pike, Rockville, Maryland. 

NRC’s Agencywide Documents Access 

and Management System (ADAMS): 

Publicly available documents created or 

received at the NRC are available 

electronically at the NRC’s Electronic 

Reading Room at http://www.nrc.gov/ 

reading-rm/adams.html. From this page, 

the public can gain entry into ADAMS, 

which provides text and image files of 

NRC’s public documents. If you do not 

have access to ADAMS or if there are 

problems in accessing the documents 

located in ADAMS, contact the NRC’s 

PDR reference staff at 1–800–397–4209, 

301–415–4737, or by e-mail to 

pdr.resource@nrc.gov. 

FOR FURTHER INFORMATION CONTACT: 

Barry W. Miller, Senior Project Manager, 

Licensing Processes Branch, Mail Stop: 

O–12 D3, Division of Policy and 

Rulemaking, Office of Nuclear Reactor 

Regulation, U.S. Nuclear Regulatory 

Commission, Washington, DC, 20555– 

0001; telephone 301–415–4117 or e-mail 

at Barry.Miller@nrc.gov. 

Dated at Rockville, Maryland, this 17th day 

of May 2010. 

For the Nuclear Regulatory Commission. 

Michael D. McCoppin, 

Acting Chief, Licensing Processes Branch, 

Division of Policy and Rulemaking, Office 

of Nuclear Reactor Regulation. 

Revised Model Proposed No Significant 

Hazards Consideration Determination 

for Plant-Specific Adoption of 

Technical Specifications Task Force 

Traveler TSTF–475, Revision 1, 

‘‘Control Rod Notch Testing Frequency 

and SRM Insert Control Rod Action’’ 

Description of amendment request: 

[(1) The proposed amendment would 

change the frequency of control rod 

notch testing, as specified in technical 

specification (TS) surveillance 

requirement (SR) [3.1.3.2], from at least 

once per 7 days to at least once per 31 

days. The purpose of this SR is to 

confirm control rod insertion capability 

which is demonstrated by inserting each 

partially or fully withdrawn control rod 

at least one notch and observing that the 

control rod moves. This ensures that the 

control rod is not stuck and is free to 

insert on a scram signal. (2) The 

proposed amendment would add the 

word ‘‘fully’’ to the Action for TS 

Limiting Condition for Operation (LCO) 

[3.3.1.2] Required Action E.2 to clarify 

the requirement to insert fully all 

insertable control rods in core cells 

containing one or more fuel assemblies 

when the required source range monitor 

(SRM) instrumentation is inoperable. 

(3)] The proposed amendment would 

revise Example 1.4–3 in Section 1.4 

‘‘Frequency’’ to clarify that the 1.25 

surveillance test interval extension in 

SR [3.0.2] is applicable to time periods 

discussed in NOTES in the 

‘‘SURVEILLANCE’’ column in addition 

to the time periods in the 

‘‘FREQUENCY’’ column. The licensee 

stated that the proposed amendment is 

based on Nuclear Regulatory 

Commission (NRC)-approved Technical 

Specifications Task Force (TSTF) 

change Traveler TSTF–475, Revision 1, 

‘‘Control Rod Notch Testing Frequency 

and SRM Insert Control Rod Action.’’ 

The availability of this change to the 

Standard Technical Specifications (STS) 

was announced in the Federal Register 

on November 13, 2007 (72 FR 63935), as 

part of the consolidated line item 

improvement process. 

Basis for proposed no significant 

hazards consideration determination: 

As required by 10 CFR 50.91(a), an 

analysis of the issue of no significant 

hazards consideration is presented 

below. 

1. Does the proposed amendment involve 

a significant increase in the probability or 

consequences of an accident previously 

evaluated? 

Response: No. 

The proposed change to SR [3.1.3.2] 

reduces the frequency of control rod notch 

testing. Changing the frequency of testing is 

not expected to have any significant impact 

on the reliability of the control rods to insert 

as required on a scram signal. The proposed 

change to the Required Action E.2 for LCO 

[3.3.1.2] merely clarifies the intent of the 

action. The proposed change to revise 

Example 1.4–3 in Section 1.4 ‘‘Frequency’’ 

clarifies the applicability of the 1.25 

surveillance test interval extension. There are 

no physical plant modifications associated 

with this change. The proposed amendment 

would not alter the way any structure, 

system, or component (SSC) functions and 

would not alter the way the plant is operated. 

As such, the proposed amendment would 

have no impact on the ability of the affected 

SSCs to either preclude or mitigate an 

accident. Therefore, the proposed change 

does not involve a significant increase in the 

probability or consequences of an accident 

previously evaluated. 

2. Does the proposed amendment create 

the possibility of a new or different kind of 

accident from any accident previously 

evaluated? 

Response: No. 

The proposed amendment would not 

change the design function or operation of 

the SSCs involved and would not impact the 

way the plant is operated. As such, the 

proposed change would not introduce any 

new failure mechanisms, malfunctions, or 

accident initiators not already considered in 

the design and licensing bases. Therefore, the 

proposed change does not create the 

possibility of a new or different kind of 

accident from any previously evaluated. 

3. Does the proposed amendment involve 

a significant reduction in a margin of safety? 

Response: No. 

The margin of safety is associated with the 

confidence in the ability of the fission 

product barriers (i.e., fuel cladding, reactor 

coolant pressure boundary, and containment 

structure) to limit the level of radiation to the 

public. There are no physical plant 

modifications associated with the proposed 

amendment. The proposed amendment 

would not alter the way any SSC functions 

and would not alter the way the plant is 

operated. The proposed amendment would 

not introduce any new uncertainties or 

change any existing uncertainties associated 

with any safety limit. The proposed 

amendment would have no impact on the 

structural integrity of the fuel cladding, 

reactor coolant pressure boundary, or 

containment structure. Based on the above 

considerations, the NRC staff concludes that 

the proposed amendment would not degrade 

the confidence in the ability of the fission 

product barriers to limit the level of radiation 

to the public. Therefore, the proposed change 

does not involve a significant reduction in a 

margin of safety. 


wwoods2 on DSK1DXX6B1PROD with NOTICES_PART 1
29588 Federal Register / Vol. 75, No. 101 / Wednesday, May 26, 2010 / Notices 

Based on this review, it appears that 

the three standards of 10 CFR 50.92(c) 

are satisfied and the requested 

amendment involves no significant 

hazards consideration. 

[FR Doc. 2010–12708 Filed 5–25–10; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2010–0186] 

Notice of Availability of the Models for 

Plant-Specific Adoption of Technical 

Specifications Task Force Traveler 

TSTF–501, Revision 1, ‘‘Relocate 

Stored Fuel Oil and Lube Oil Volume 

Values to Licensee Control’’ 

AGENCY: Nuclear Regulatory 

Commission (NRC). 

ACTION: Notice of availability. 

SUMMARY: As part of the consolidated 

line item improvement process (CLIIP), 

the NRC is announcing the availability 

of the enclosed model application (with 

model no significant hazards 

consideration determination) and model 

safety evaluation (SE) for the plantspecific adoption of Technical 

Specifications Task Force (TSTF) 

Traveler TSTF–501, Revision 1, 

‘‘Relocate Stored Fuel Oil and Lube Oil 

Volume Values to Licensee Control.’’ 

TSTF–501, Revision 1, is available in 

the Agencywide Documents Access and 

Management System (ADAMS) under 

Accession Number ML090510686. The 

proposed changes would revise 

Technical Specifications (TS) 3.8.3, 

‘‘Diesel Fuel Oil, Lube Oil, and Starting 

Air,’’ by relocating the current stored 

diesel fuel oil and lube oil numerical 

volume requirements from the TS to the 

TS Bases so that it may be modified 

under licensee control. This CLIIP 

model SE will facilitate expedited 

approval of plant-specific adoption of 

TSTF–501, Revision 1. 

Documents: You can access publicly 

available documents related to this 

notice using the following methods: 

NRC’s Public Document Room (PDR): 

The public may examine and have 

copied for a fee publicly available 

documents at the NRC’s PDR, Public 

File Area O1 F21, One White Flint 

North, 11555 Rockville Pike, Rockville, 

Maryland. 

NRC’s Agencywide Documents Access 

and Management System (ADAMS): 

Publicly available documents created or 

received at the NRC are available 

electronically at the NRC’s Electronic 

Reading Room at http://www.nrc.gov/ 

reading-rm/adams.html. From this page, 

the public can gain entry into ADAMS, 

which provides text and image files of 

NRC’s public documents. If you do not 

have access to ADAMS or if there are 

problems in accessing the documents 

located in ADAMS, contact the NRC’s 

PDR reference staff at 1–800–397–4209, 

301–415–4737, or by e-mail to 

pdr.resource@nrc.gov. 

The model application (with model 

no significant hazards consideration 

determination) and model SE for the 

plant-specific adoption of TSTF–501, 

Revision 1, are available electronically 

under ADAMS Package Accession 

Number ML100850069. The NRC staff 

disposition of comments received to the 

Notice of Opportunity for Comment 

announced in the Federal Register on 

August 20, 2009 (74 FR 42131–42138), 

is available electronically under 

ADAMS Accession Number 

ML100920563. 

FOR FURTHER INFORMATION CONTACT: 

Barry W. Miller, Senior Project Manager, 

Licensing Processes Branch, Mail Stop: 

O–12 D1, Division of Policy and 

Rulemaking, Office of Nuclear Reactor 

Regulation, U.S. Nuclear Regulatory 

Commission, Washington, DC, 20555– 

0001; telephone 301–415–4117 or e-mail 

at Barry.Miller@nrc.gov. 

SUPPLEMENTARY INFORMATION: TSTF– 

501, Revision 1, is applicable to all 

nuclear power reactors. Licensees 

opting to apply for this TS change are 

responsible for reviewing the NRC 

staff’s model SE, referencing the 

applicable technical justifications, and 

providing any necessary plant-specific 

information. The NRC will process each 

amendment application responding to 

this notice of availability according to 

applicable NRC rules and procedures. 

The model does not prevent licensees 

from requesting an alternate approach or 

proposing changes other than those 

proposed in TSTF–501, Revision 1. 

However, significant deviations from 

the approach recommended in this 

notice or the inclusion of additional 

changes to the license require additional 

NRC staff review and would not be 

reviewed as a part of the CLIIP. This 

may increase the time and resources 

needed for the review or result in NRC 

staff rejection of the license amendment 

request (LAR). Licensees desiring 

significant deviations or additional 

changes should instead submit an LAR 

that does not claim to adopt TSTF–501, 

Revision 1. 

The NRC staff requests that each 

licensee applying for the changes 

proposed in TSTF–501, Revision 1, 

include their current licensing basis for 

fuel and lube oil storage requirements in 

their LAR. 

Dated at Rockville, Maryland, this 14th day 

of May 2010. 

For the Nuclear Regulatory Commission. 

Michael D. McCoppin, 

Acting Chief, Licensing Processes Branch, 

Division of Policy and Rulemaking, Office 

of Nuclear Reactor Regulation. 

[FR Doc. 2010–12716 Filed 5–25–10; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2010–0184] 

Office of New Reactors: Proposed 

NUREG–0800; Standard Review Plan 

Section 13.6.6, Draft Revision 0 on 

Cyber Security Plan 

AGENCY: Nuclear Regulatory 

Commission (NRC). 

ACTION: Solicitation of public comment. 

SUMMARY: The NRC staff is soliciting 

public comment on NUREG–0800, 

‘‘Standard Review Plan for the Review of 

Safety Analysis Reports for Nuclear 

Power Plants,’’ on a proposed Standard 

Review Plan (SRP) Section 13.6.6 on 

‘‘Cyber Security Plan’’ (Agencywide 

Documents Access and Management 

System (ADAMS) Accession No. 

ML093560837). The Office of Nuclear 

Security and Incident Response is 

issuing the SRP Section 13.6.6 

(Enclosure 1) for the purpose of 

soliciting comments from the entities 

that we understand have a need to 

comment on the proposed draft 

guidance. 

The NRC staff issues notices to 

facilitate timely implementation of the 

current staff guidance, to facilitate 

activities associated with the review of 

amendment applications, and to 

facilitate activities associated with 

review of applications for design 

certification and combined license by 

the Office of New Reactors. The NRC 

staff intends to incorporate the final 

approved guidance into the next 

revision of NUREG–0800, SRP Section 

13.6.6 and Regulatory Guide 1.206, 

‘‘Combined License Applications for 

Nuclear Power Plants (LWR Edition),’’ 

June 2007. 

DATES: Comments must be filed no later 

than 30 days from the date of 

publication of this notice in the Federal 

Register. Comments received after this 

date will be considered practical to do 

so, but the Commission is able to ensure 

consideration only for comments 

received on or before this date. 

ADDRESSES: You may submit comments 

by any one of the following methods. 

Please include Docket ID NRC–2010– 


wwoods2 on DSK1DXX6B1PROD with NOTICES_PART 1