LR-N12-0028, Supplement to Application for Tech Spec Change TSTF-477 Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Tech Specs Using Consolidated Line Item Improvement Process

Supplement to Application for Tech Spec Change TSTF-477 Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Tech Specs Using Consolidated Line Item Improvement Process

ML12026A458
Person / Time
Site:	Hope Creek
Issue date:	01/26/2012
From:	Jamila Perry Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N12-0028
Download: ML12026A458 (5)

Text

PSEG p.o. Box 236, Hancocks Bridge, NJ 08038-0236 OPSEG NuclearLLC 10 CFR 50.90 JAN 26 2012 LR-N 12-0028 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354

Subject:

Supplement to Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process

Reference:

(1) LR-N11-0068, Letterfrom PSEG to NRC, "Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process," dated 2/28/2011 In Reference 1, PSEG Nuclear LLC (PSEG) submitted a license amendment request for the facility operating license listed above. The proposed amendment would modify the TS by adding an action statement for two inoperable control room AC subsystems to the plant specific TS. Additionally, because Hope Creek has not implemented NUREG-1433, Rev. 3, "Standard Technical Specifications (STS), General Electric Plant, BWRl4," PSEG proposes additional TS changes to ensure consistency with STS. These additional changes align HCGS TS with STS to allow for direct use of TSTF-477. The changes to align with STS involve addition of separate TS for the control room air conditioning system.

Subsequent to the submittal of Reference 1, additional review discovered that two TS mark-up pages provided in Reference 1 contained numbering and formatting errors. The specific items are:

• TS page 3/47-6; LCO 3.7.2 should have been renumbered to 3.7.2.1 to be consistent with the proposed changes of adding a new LCO 3.7.2.2

• TS page 3/4 7-6a; the header should not have contained the numbering "3/4.7.2" for consistency in page formatting The revised marked up TS pages are included as Attachment 1 to this letter.

LR~N12-0028 Page 2 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 bases for concluding that the proposed license amendment does not involve a significant hazards consideration. No regulatory commitments are contained in this submittal.

If you have any questions or require additional information, please do not hesitate to contact Ms. Emily Maguire at (856) 339-1023.

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

JAN 262012 Executed on _ _ _ _ _ _ __

(Date)

Sincerely, i1r;~

Site Vice President - Hope Creek Attachments:

1. Revised Marked Up TS Pages Cc: W. Dean, Administrator, Region I, NRC R. Ennis, Project Manager ~ USNRC NRC Senior Resident Inspector, Hope Creek P. Mulligan, Manager IV, NJBNE K. Yearwood - Commitment Tracking Coordinator - Hope Creek L. Marabella - Corporate Commitment Tracking Coordinator

LR~N12~0028 Attachment 1 REVISED TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES Facility Operating License NPF~57 Technical Specification 3/4.7.2 3/4 7~6 3/4.7.2 3/47-6a

r w:a.tJon system subsystems APl?LlCAEILlTY:

ACTIO~!

a. In OPERATIONAL COND!TION 1, 2 or 3

1. With onE! control room emergency filtration subsystem ,

inoperable for reasons other than Conci t1011 a. 2. restore the inoperabl.e subsystem to OPERABLE status w:!.thin '1 days or be in at least BOT SHOTOOIN ttithin the next :1.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and in COLO SHUfOO~ 'l>fi,thin the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2. iUth OM ordue more control. roo~ emergency filtration subsystems to an inoperable control room envelope (CRE}

boundary 'I ,

inoperab~e

a. lmmed1etelYt initiate action to implement mitiq!lt:ing

-actions; and

b. Within :H hoursl verifY'mitigating actions ensur;e CRE e>¢cupanl:'; el¢pO$W:~$ to radiolQ{dical and c:;!hemiea.t hazards will not exceed the limits and aotions to mitigate exposure to smoke hazaid:is are takent aM

. c. Within 90 clays, restore the CRE boundary to operable status; .

Otherwise, be in at least HOT Sl1tlTDONI1 "li thin the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLO SHOTOl)'I'm within the following 24 nou:cs.

b. In Ol:'ERATIONrJ. CONDITION 'II:

1. With one control room emergenoy filtration subsystem inQperable for reasons other than Condition h.S, reste>re the inoperable subsystem to Ol:'ll:AAgLt status Within ., days or initiate and maintain operation of the OPERABLE subsystem in the presrsurlzation/rec:irc:ullltion mode of operation.

• When recently 7irradiated fuel is being handled in the secondary containment I

and during oper~tions with a poten.tial for draining the reactor vessel.

'liThe main control room envelope {CaE} boundary may b¢ opened intermittently under administrative ccmtxol. .

Amendment No. 173

PLANT SYSTEMS f47.. CONTROL ROOM EMERGENCY FILTRATION SYSTEM LIMITING CONDITION FOR OPERATION (continued)

2. With both control room emergency filtration subsystems inoperable for reasons other than Condition b.3, suspend handling of recently irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.

3. With one or more control room emergency filtration subsystems inoperable due to an inoperable CRE boundary##, immediately suspend handling of recently irradiated fuel and operations with a potential for draining the vessel.

c. The provisions of Specification 3.0.3 are not applicable in Operational Condition*.

@j SURv~LNCE REQUI REMENTS

• When recently irradiated fuel is being handled in the secondary containment and during operations with a potential for draining the reactor vessel.

T s does ~t reQUirrstarting t e non-ru ing cont¢! emerge cy filtrati/n sUbs~tem. ,

The main control room envelope (CRE) boundary may be opened intermittently under administrative control.

HOPE CREEK 3/47-6a Amendment No. 187