ML20101D408

Application for Amends to Licenses NPF-68 & NPF-81, Converting Existing TS to Improve for Westinghouse Plants as Represented by NUREG-1431

ML20101D408
Person / Time
Site:	Vogtle
Issue date:	03/05/1996
From:	Mccoy C GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20101D410	List: ML20101D408 ML20101D415
References
RTR-NUREG-1431 LCV-0603-I, LCV-603-I, TAC-M92131, TAC-M92132, NUDOCS 9603200251
Download: ML20101D408 (2)

Text

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l \ Georgia Power Company l 40 inverness Center Parkway

, , l l Post O*1ce Box 1295 i

, Brtm>ngham, Ata,ama 3520t l Telephone 205 877-7122 l L

C. K. McCoy Georgia Power Vce Presdent, Nuclear i Vogtfe Protect the soutten electic system March 5, 1996 l LCV-0603-1 Docket Nos. 50-424 50-425

! Tac Nos. M92131 M92132 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555 Gentlemen:

VOGTLE ELECTRIC GENERATING PLANT PROPOSED CONVERSION OF THE UNIT 1 AND UNIT 2 TECHNICAL SPECIFICATIONS BASED ON NUREG-1431 By letter dated May 1,1995, (LCV-0603) Georgia Power Company (GPC) proposed to amend the Vogtle Electric Generating Plant (VEGP) Unit 1 and Unit 2 Technical Specifications (TS). The proposed changes would, in part, convert the existing VEGP TS to the improved TS for Westinghouse plants as represented by NUREG-1431. By letters dated December 21,1995, (LCV-0603-D) and January 30,1996, (LCV-0603-E) GPC revised our May 1,1995, submittal in response to requests for additional intbrmation from the NRC staff as well as other issues that were identified subsequent to our May 1,1995, submittal.

Subsequent to our January 30,1996, submittal, several additional issues have been identified that need to be addressed as described in the following paragraphs.

1. The Completion Times for LCO 3.2.4 Required Actions A.4, A.5, and A.6 need to be revised to reference thermal power as limited by Required Action A.2.2 in

, addition to Required Action A.I. That is, the Completion Time should read as i follows:

" Prior to i.ncreasing TilERMAL POWER above the limit of Required Action A.1 and A.2.2."

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! . U. S. Nuclear Regulatory Commission LCV-0603-1 Page 2 Once Required Action A.1 has been performed, Required Action A.2.1 requires l quadrant power tilt ratio (QPTR) to be checked once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while

! Condition A is applicable. If QPTR continues to increase. Required Action A.2.2 requires further reductions in power. Therefore, the Completion Times of Required Actions A.4, A.5, and A.6 should reference the most limiting condition.

2. The LCO discussion for LCO 3.4.7,"RCS Loops - MODE 5. Loops Filled,"

needs to be revised with respect to the requirements for an operable steam generator. Specifically, the additional requirement that RCS pressure be l maintained greater than 100 psig since the most recent filling and venting has been added. This will provide additional assurance that gases will not come out of solution at low RCS pressures so that natural circulation can be initiated and maintained.

3. There is a typographical error on the page identified as " INSERT FOR PAGE B 3.3-53." This page appears in the Bases for LCO 3.3.1 immediately following page B 3.3-53. The equation for axial offset has a minus sign in the denominator that should be a phis sign.

4. In our December 21,1995, revised submittal, we revised the Bases for SR 3.4.12.1 to state that the safety injection pumps must be rendered incapable of injecting into the RCS through at least two independent means such that a single failure or single action will not result in an injection into the RCS. (This is in lieu of stating that the pump hand switch will be in pull-to-lock and a discharge valve will be closed.) llowever we failed to revise our Discussion of Change (DOC) 30. The Bases as proposed by our December 21,1995, submittal states the criteria for rendering the safety injection pumps incapable ofinjecting into l the RCS as opposed to prescribing how that will be accomplished. Our l proposed Bases provides the necessary assurance that an inadvertant safety injection via the safety injection pumps will not occur while providing flexibility for meeting this requirement.

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5. The definition for the Core Operating Limits Report contains an incorrect reference to Specification 5.9.1.6. The correct reference is Specification 5.6.5.

Similarly, the definition for the Pressure Temperature Limits Report references Specification 5.9.1.7 when the correct reference is Specification 5.6.6.

I

.- U. S. Nuclear Regulatory Commission LCV-0603-1 i Page 3

6. In the current submittal, for SR 3.3.1.7 there is a note that SR 3.3.1.7 is "not required to be performed for source range instrumentation prior to entering l

mode 3 from mode 2 until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entry into mode 3" This note provides for mode 3 entry and the attendant source range NI energization on controlled shutdowns prior to requiring the performance of the source range COT. To I make the liFASA COT requirements consistent with the source range NI COT  !

requirements, this same note needs to be added to SR 3.3.8.1, ilFASA COT.

The basis for this change is addressed in RTS discussion of change 63, and the attendant significant hazards evaluation applies to this change.

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7. Specification 5.6.6 has been revised at the request of the NRC staff to provide j appropriate references for the approval of the Pressure and Temperature Limits l Report. I

8. Surveillance Requirement 3.5.6.1.c contains an error. The current TS requirement is that the three trisodium phosphate baskets be verified to contain a total of between 11,484 pounds (220 cubic feet) and 14,612 pounds (260 cubic feet). Surveillance Requirement 3.5.6.1.c, as it is presently worded, requires i

that each basket be verified to contain 211,484 pounds (220 cubic feet) and s l 14,612 pounds (260 cubic feet). Therefore, improved TS SR 3.5.6.1.c needs to be revised to be consistent with the current TS requirement.

Enclosed are marked-up pages, as appropriate, reflecting these changes. l l

I Sincerely, 1

C. K. hicCoy CKM/NJS Enclosure xc: Georeia Power Comnany hir. J. B. Beasley, Jr.

Air. h1. Sheibani NORN1S U. S. Nuclear Reculatory Commission Nir. S. D. Ebneter, Regional Administrator hir. I., L. Wheeler. Licensing Project hianager, NRR hir. C. R. Ogle, Senior Resident Inspector, Vogtle