LR-N11-0002, Supplement to License Amendment Request H10-01, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee.

Supplement to License Amendment Request H10-01, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee.

ML110200059
Person / Time
Site:	Hope Creek
Issue date:	01/10/2011
From:	Jamila Perry Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N11-0002
Download: ML110200059 (7)

Text

PSEG Nuclear LLC I -- I P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 PSEG N

Nuclear LLC 10 CFR 50.90 JAN 1 0 2011 LR-N1-'0002 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354

Subject:

Supplement to License Amendment Request 1-110-01, APPLICATION FOR TECHNICAL SPECIFICATION CHANGE REGARDING RISK-INFORMED JUSTIFICATION FOR THE RELOCATION OF SPECIFIC SURVEILLANCE FREQUENCY REQUIREMENTS TO A LICENSEE CONTROLLED PROGRAM

References:

(1) Letter from PSEG to NRC, "Application for Technical Specification change regarding risk-informed justification for the relocation of specific surveillance frequency requirements to a licensee controlled program," dated March 19, 2010 (ML100900224)

(2) Letter from PSEG to NRC, "Response to Request for Additional Information-Risk Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program," dated July 28, 2010 (ML102230417)

(3) Email from NRC to PSEG, "Request for Camera Ready Pages - Hope Creek TSTF-425," dated November 22, 2010 In Reference 1, PSEG Nuclear LLC (PSEG) submitted a license amendment request for Hope Creek Generating Station (HCGS). The request would modify HCGS Technical Specifications (TS) by relocating specific surveillance frequencies to a licensee-controlled program, the Surveillance Frequency Control Program, with the implementation of Nuclear Energy Institute (NEI) 04-10, "Risk Informed Method for Control of Surveillance Frequencies."

PSEG requested that the proposed license amendment be approved by the NRC by March 31, 2011 with a 120 day implementation period. In Reference 2, PSEG responded to the NRC's request for additional information regarding the license amendment request. In Reference 3, the NRC requested camera-ready pages. While PSEG was reviewing the significant number of technical specification pages affected by this change, a few editorial corrections were identified.

By this letter, PSEG is submitting page corrections to the NRC for review. The revised pages are editorial in nature and do not modify the intent of the license amendment request.

95-2168 REV. 7/99

PSEG has reviewed the information supporting a finding of no significant hazards consideration that was provided to the NRC in Reference 1. The additional information provided in this letter does not affect the conclusion that the proposed license amendment does not involve a significant hazards consideration.

There are no regulatory commitments contained in this submittal.

If you have any questions or require additional information, please do not hesitate to contact Mrs. Erin West at (856) 339-5411.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on I lO(LtI tDate)

Sincerely,

ýonF. Perry Site Vice Presiden'td- Hope Creek Attachment Marc L. Dapas, Acting Regional Administrator - NRC Region I R. Ennis, Project Manager - USNRC NRC Senior Resident Inspector - Hope Creek P. Mulligan, Manager IV, NJBNE Commitment Coordinator - Hope Creek PSEG Commitment Coordinator - Corporate

ATTACHMENT 1 TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES:

LICENSE AMENDMENT TO ADOPT TSTF-425. REVISION 3.

"RELOCATE SURVEILLANCE FREQUENCIES TO LICENSEE CONTROL" The following HCGS Technical Specifications pages (Facility Operating License NPF-57) are affected by this supplement:

3/4 3-31 3/4 3-66 3/4 3-55 3/4 3-67

TABLE 4.3.2.1-1 (Continued)

ISOLATION ACTUATION INSTRUPIENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CHANNEL. FUNCTIOQPAJ CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK) TEST a cALIBRATION()SURVEILLANCE REQUIRED HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION (Continued)

h. HPCi Torus Compartment Temperature - High NA 1, 2, 3

i. Drywell Pressure - High NA 1, 2, 3

j. Manual initiation I NA 9 NA 1, 2, 3 7- RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION

a. Reactor L Vessel Water Level Low, Level 3 71, 2, 3

b. Reactor Vessel (RHR Cut-in Permissive) Pressure - High NA 1, 2, 3

c. Manual Initiation NA *(a) NA 1, 2, 3 When handling recently irradiated fuel in the secondary containment and during operations with a potential for draining the reactor vessel.

• When any turbine stop valve is greater than 90% open and/or when the key-loc s switch is in the Norm position. A*7 (a) Manual initiation switches shall be tested at st cr' 1-mo~rlts_ All other circuitvasociated with manual initiation shall receive a C tA IONAL TEST t e~s c e s as part of circuitry required to be tested for automatic s (b) Each train or logic channel shall be teste a ea v o er ,d HOPE CREEK 3/4 3-31 Amendment No. 166

TABLE 4.3.5.1-1 REACTOR CORE ISOLATION COOLnIG SYSTEM ACTUATION INSTRUMENTATION .1 ITLL.UN.CE ! PE; '-

CHANNEL CHANNEL. FUNCTIONAL CHANNEL FUNCTIORAI, UMrS CHECK TEb)b CzAZMIz rOlq~b2

a. Reactor Vessel o Water Level Low Low, Level 2

b. Reactor Vessel Water Level - High, Level 8 C. Condensate Storage Tank Level - L~ow NA

d. Manual Initiation NA) NA (a) Manual initiation switches shall be tested All other circuit9- I associated with manual initiation- shall receive a CHAUEL FUNCTIONAL TEST e ce > -9 da) as part of circuitry required to be tested for automatic system actuation. 4 I~~i/<5SAe ,2 7 4 Lýa (In/~/~ -e 46&

HOPE CREEK 3/4 3-55 Amendmen2t No. 165

TABLIE 4.3.7.1-1 RADIAI-ON-MONITORIbrG INSTRUMENTATION SURVEILLANCE kEQUIREMENTS OPERATIONAL CHANNEL CONDITIONS FOR CHIANNEL FUNMTION~AL CHANNEL WHICH SURVEILLANCE INSTRUMENTATION CE[ECK(-Q) TES T (4,5 CAL1B3AT ION (A~) REQUIRED

1. Control Room Vautilation Radiation Monitor 1, 2, 3, and *

2. Area Monitors

a. Criticality Monitors

1) New Fuel Storage Vault A

2) Spent Fuel Storag- Pool

b. Control Room Direct At all times Radiation Monitor

3. Reactor Auxiliaries Cooling At all times Radiation Monitor

4. SaEfety Auxiliaries Cooling Radiation Monitor / At all times

5. Offgas Pre-treatment Radiation Monitor K **

"I HOPE CREEK 314 3-66 Amendment No. 156 1 A

TABLE" 4.3.7.1-1 (Continued)

RADIATIObi MONITORING INSTRUMENTATION SURVEILLANCE .REQUIREMENTS TABLE NOTATION W1ith fuel in the new MWith spentfuel storage fuel storagevrault.

pool.

'Wbhen recently irradiated fuel is being handled in the secondary containment and during operations with the potential for draining the reactor vessel. I "When the offgas treatment system is operating.

pf N

HOPE CREEK 314 3-67 Amendment No. 156