ML20207J953

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Application for Amend to License NPF-5,adding &/Or Clarifying Operability & Surveillance Requirements Re ATWS Recirculation Pump Trip Instrumentation
ML20207J953
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 07/18/1986
From: Bechman J, Beckham J
GEORGIA POWER CO.
To: Muller D
Office of Nuclear Reactor Regulation
Shared Package
ML20207J957 List:
References
1112, 1112T, SL-871, TAC-55543, NUDOCS 8607290301
Download: ML20207J953 (7)


Text

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, , Georgia Power Corrpany 333 Piedmont Avenue i Atlanta. Georgia 30308 l Telephone 404 526-7020 Mathng Address Post Office Box 4545 Atlanta, Georgia 30302 l GeorgiaPower ce P er : l an Gener al Manager Nuclear Operations g(,g7]  ;

1112t July 18,1986 Director of Nuclear Reactor Regulation Attention: Mr. D. Muller, Project Director BWR Project Directorate No. 2 Division of Boiling Water Reactor Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC DOCKET 50-366.

OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 TECHNICAL SPECIFICATIONS CHANGES PERTAINING TO RECIRCULATION PUMP TRIP Gentlemen:

Georgia Power Company's (GPC) submittal of April 23, 1984, requested changes to the Plant Hatch Unit 2 Technical Specifications that would add and/or clarify operability and surveillance requirements pertaining to the Anticipated Transient Without Scram (ATWS) Recirculation Pump Trip (RPT) instrumentation. Following discussions with the NRC staff regarding the April 23, 1984, submittal , two areas requiring revision were identified. These are: 1) addition of operability and surveillance requirements for the End-of-Cycle (E0C) RPT function and 2) clarification of previously proposed operability and surveillance requirements for the ATWS RPT function. For the sake of clarity and simplification, we are submitting the enclosed infonnation which supersedes in entirety the April 23, 1984, submittal and encompasses the two areas of concern.

The Plant Review Board and the Safety Review Board have reviewed the proposed changes.

Enclosure 1 provides a detailed description of each proposed change and the circumstances necessitating the change request.

Enclosure 2 details the bases for our determination that the proposed changes do not involve significant hazards considerations. j 8607290301 860718 6 DR ADOCK 0500 e \

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GeorgiaPower d Director of Nuclear Reactor Regulation l Attention: Mr. D. Muller, Project Director BWR Project Directorate No. 2 l July 18,1986 l Page Two Enclosure 3 provides page change instructions for incorporating the l proposed changes. The proposed changed Technical Specifications pages follow Enclosure 3.

Payment of a filing fee is not required, since this submittal supersedes a previous submittal for which such fee was paid.

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We request that this amendment be issued with an effective date to be no later than 60 days from the date of amendment issuance, to allow for orderly incorporation of associated procedure changes.

Pursuant to the requirements of 10 CFR 50.91, a copy of this letter and all applicable enclosures will be sent to Mr. J. L. Ledbetter of the Environmental Protection Division of the Georgia Department of Natural Resources.

Mr. J. T. Beckham, Jr. states that he is Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief, the facts set forth in this letter are true.

GEORGIA POWER COMPANY By: hd -h g J. T. Beckham, Jr./

Sworn to and subscribed before me this 18th day of July 1986.

xth / kb u/ Notary Public R d' b,I[.#/,",[gageog,a Enclosures c: Georr f a Power Company Nuclear Regulatory Commission Mr. i. P. O'Reilly Dr. J. N. Grace, Regional Administrator Mr. H. C. Nix, Jr. Senior Resident Inspector

! GO-NORMS State of Georgia Mr. J. L. Ledbetter 1112t 700775 y )

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GeorgiaPower A ENCLOSURE 1

's. NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 TECHNICAL SPECIFICATIONS CHANGES

, PERTAINING TO RECIRCULATION PUMP TRIP s di BASIS FOR CHANGE REQUEST AND SAtuf EVKGATION

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", $ Proposed change 1 will provide clear surveillance requirements and setpoints for demonstrating operability of the Anticipated Transient Without

, Scram' (ATWS) Recirculation Pump Trip (RPT) instrumentation. These instruments trip the recirculation pump motor-generator set drive motor breakers to reduce reactivity during the postulated ATWS event. These instruments s

appear' in Table 3.3.1-1, " Reactor Protection System Instrumentation, and are pres However, operability identified by footnote "j " to this table. and

- , surveillance requirements are not explicitly provided. Actions and surveillance requirements provided in Tables 3.3.1-1 and 4.3.1-1 apply only to

? the Reactor Protection System (RPS) instrumentation. Due to this situation, e Hatch Unit 2 Plant Procedures now implement requirements similar to those contai'ned in the Hatch Unit 1 Technical Specifications, which do provide explicit operability and surveillance requirements for this instrumentation.

- Proposed change 1 adds a new section 3/4.3.9.1, "ATWS Recirculation Pump

'" Trip Actuation Instrumentation." Based on the corresponding section in BWR

' Standard Technical Specifications, this section contains operability requirements, action statements, instrument setpoints, and surveillance

< requirements for the ATWS RPT instruments. Requirements have been chosen to be consistent with those contained in the Hatch Unit 1 Technical Specifications and, as previously noted, already implemented in the Unit 2 procedures.

Some modifications to the Standard Technical Specifications are necessary in order to accomodate the Hatch design. BWR Standard Technical Specifications assume mul tiple, redundant channels for the ATWS RPT instrumentation, and thus presume the capability to trip individual channels 3without initiating an RPT. However, the design in use at Plant Hatch is the " original BWR 4 design" as provided in General Electric Topical Report NEDE-31096-P. In this design, the trip of any single RPV water level or high reactor pressure channel will trip one of the recirculation pump motor-generator sets. Thus, the BWR Standard Technical Specifications have been revised to reflect the correct number of required operable channels and the fact that individual channels cannot be tripped or made inoperable without incurring an RPT. Surveillance requirements are consistent with those for Plant Hatch Unit 1, which uses the same ATWS RPT logic and dasign.

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GeorgiaPower A ,

ENCLOSURE 1 (Continued)

NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 ,

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TECHNICAL SPECIFICATIONS CHANGES PERTAINING TO RECIRCULATION PUMP TRIP  !

BASIS FOR CHANGE REQUEST AND SAFETY EVKEATION Proposed change 2 adds a new section 3/4.3.9.2, "End of Cycle Recirculation Pump Trip System Instrumentation." This section provides explicit operability and surveillance requirements ' for the End-of-Cycle (EOC)

RPT function. The EOC RPT system is designed to trip the recircclation pump motor breakers in order to limit void collapse and preserve fuel therwal limit margins during certain postulated pressurization transients occurring near the '

end of cycle. Analogous to the ALMS RPT instrumentation, these instruments

are presently alluded to only by note "k" to Table 3. 3.1 -1, " Reactor Protection System Instrumentation. " Actior.s and surveillances in this table are associated with the Reactor Protection System (RPS)provided function of these instruments and not the EOC RPT function. The proposed Technical Specifications will provide explicit requirements for;the E0C RPT function and are based on BWR Standard Technical Specifications.

These proposed changes represent a clarification / expansion of actions and

surveillance requirements which are not explicitly delineated in the Technical Specifications. The instruments are currently included in the RPS Technical i

Specifications where the RPT actions and surveillance requirements are implied i

! by footnotes. The proposed changes add a new RPT section to the Technical

Specifications and delete the footnotes, thereby enhancing the control of
these functions. Note that the RPT instrumentation operability is assured by

( plant procedures currently in place. Thus, the proposed changes are ,

administrative in nature in that they change the mode of incorporation of existing requireir.cnts.

i Revised Tables of Contents ana Bases are provided to reflect these additions to the Technical Specifications. . Section 3/4.3.8, " Degraded Station Yoltage Protection Instrumentation," is also added to the Table of Contents, since it does not presently appear.

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GeorgiaPower A .

EWCLOSURE 2 NRC DOCKET 50-366 t

OPERATING LICENSE NPF-5 EDWIN I. HATCH hUCLEAR PLANT UNIT 2

. TECHNICAL SPECIFICATIONS CHANGES 1

4 PERTAINING TO RECIRCULATION PUMP TRIP 10 CFR 50.92 EVALUATION Proposed Change 1:

This change adds explicit operability and surveillance requirements for instrumentation which provides the anticipated transient without scram (ATWS) recirculation pump trip (RPT) function. ATWS RPT instruments trip the recirculation pump motor-pump generator set drive motor breakers. These instruments are presently footnoted in the Technical Specifications, but no surveillance requirements are provided.

Basis:

The proposed change does not involve a significant increase in the probability or consequences of analyzed accidents. This change provides addi tional requirements not presently included in the Technical Specifications. This change is administrative in nature, since the proposed requirements are already being met procedurally. The proposed change does not result in any new types of accidents, since no new modes of plant operation are involved.

The proposed change does not involve a significant reduction to a margin of safety. Margins of safety are unaffected by this administrative change.

This change constitutes an additional limitation, restriction, or control not presently included in the Technical Specifications. Therefore, this change is consistent with Item (ii) of " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations," page 14870 of the Federal Register, April 6,1983.

Proposed Change 2:

This change adds explicit operability and surveillance requirements for

instrumentation which provides the end-of-cycle (EOC) RPT function. E0C RPT instruments trip the recirculation pump motors. These instruments are presently footnoted in the Technical Specifications, but no requirements are provided.

Basis:

The proposed change does not involve a significant increase in the probability or consequences of analyzed accidents. This change provides additional E2-1 1112t 7/18/86 700775 #

O 8 GeorgiaPower da ENCLOSURE 2 (Continued)

NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 '

TECHNICAL SPECIFICATIONS CHANGES '

PERTAINING TO RECIRCULATION PUMP TRIP 10 CFR 50.92 EVALUATION requirements not presently included in the Technical Specifications. This change is administrative in nature, since the proposed requirements are already being met procedurally. The proposed change does not result in any new types of accidents, since no new modes of plant operation are involved.

The proposed change does not involve a significant reduction to a margin of safety. Margins of safety are unaffected by this administrative change.

This change constitutes an additional limitation, restriction, or control not presently included in the Technical Specifications. Therefore, this change is consistent with Item (ii) of " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations," page 14870 of the Federal Register, April 6,1983.

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GeorgiaPower d ENCLOSURE 3 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 TECHNICAL SPECIFICATIONS CHANGES PERTAINING TO RECIRCULATION PUMP TRIP PAGE CHANGE INSTRUCTIONS The proposed changes to Technical Specifications (Appendix A to Operating License NPF-5) would be incorporated as follows:

Remove Page Insert Page V V VI VI 3/4 3-2 3/4 3-2 3/4 3-3 3/4 3-3 3/4 3-5 3/4 3-5 3/4 3-66 3/4 3-67 3/4 3-68 3/4 3-69 3/4 3-70 3/4 3 -71 3/4 3-72 3/4 3-73 3/4 3-74 3/4 3-75 B 3/4 3-Sa B 3/4 3-5b 1112t 7/18/86

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