ML20235J448

Informs That Encl Draft Author Memo to Ja Calvo Re Summary of 870825 & 26 Meetings W/Util Concerning Tech Spec Upgrade Program Provided to Licensee.Requests That Memo Be Provided to NRC & Lpdr

ML20235J448
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/28/1987
From:	Heitner K NRC
To:	NRC
References
NUDOCS 8710010452
Download: ML20235J448 (4)

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Docket No. 50-267 MEMORANDUM'FOR: _ Jose A. Calvo, Director Project Directorate-IV Division of Reactor Projects - III, IV, V and Special Projects FROM:

Kenneth L. Heitner, Porject Manager ProjectDirectorate-IV Division of Reactor Projects - III, IV, V and Special Projects

SUMMARY

OF MEETING WITH PUBLIC SERVICE COMPANY OF COLORADO TO DISCUSS FORT ST. VRAIN TECHNICAL SPECIFICATION UPGRADE PROGRAM - AUGUST 25 AND 26, 1987 On August 25 and 26, 1987 the NRC staff met with the staff of the Public Service Company of Colorado (PSC) at Fort St. Vrain (FSV). Also in attendance

.were NRC contractors from Idaho National Engineering Laboratory (INEL) and Oak Ridge National Laboratory (0RNL). The purpose of this meeting was The to discuss the-meeting status-of'the FSV Technical Specification Upgrade Program'(TSUP).

~a ttendees are listed in Enclosure 1. The meeting agenda is Enclosure 2.

This meeting summary was prepared with References are listed'in Enclosure 3.

the assistance of Louis N. Rib, Consultant to INEL.

A proposed schedule for the completion of the TSUP, sent by NRC to PSC (Ref.1), was discussed and modified at this meeting. A review of the proposed PSC responses to the NRC requests for additional information (RAls) was discussed during the major part of the meeting. 'The new classification The status for.these responses are listed in the tables of Enclosure 5.

acceptance. status will be verified when PSC formally submits the RAI responses in the near future. The next meeting on TSUP was projected to be in 8 weeks.

PSC suggested a date of about 11/15/87 or about two weeks after the PSC sub-mission of the RAI responses on the Cooling Functions.

The NRC staff has met previously with the PSC staff, and the NRC contractors, on the subject of TSUP (Ref. 2 and 3). These meetings were based primarily on the NRC staff review (Ref. 4) of the final draft of the FSV upgraded Technical Specifications (TS). As a result of these meetings, the NRC comments contained in Reference 5 were reviewed and categorized into one of six categories (listed in e.g., Ref. 2 and 3). For ease of reference, they are noted in Enclosure 4.

Reference 5 summarized the NRC/PSC meeting of 12/18/86 and transmitted RAIs.

Following these meetings, PSC submitted docu-mentation for comment resolution that were reached at the previous meetings with NRC (Ref. 6) Subsequent RAIs were sent to PSC by NRC. These include:

(1) References 7 & 8, RAls on the final draft Electrical Technical Specifica-tions; (2) Reference 9 transmitted RAIs on safety related cooling functions to PSC; and DNT

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-(3) Reference.10 transmitted RAls to PSC on category'A#, 0 and 0# items s

(Defined in Enclosure _4_J__/The PSC proposed responses to the RAls submitted F Tn~the above references,_ formed the basis for this meeting with PSC.

As the basis for the completion of the TSUP review, the staff discussed the NRC letter of. S/30/86, " Comments on the Final Draft of the FSV Upgraded Technical Specifications" (Ref. 4). The crogress of the TSUP review is focused on four

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items, which were expanded int > a proposed review completion schedule (Ref.1).

The milestones for the first three line items in Fig. 1 (Ref. 1) are on schedule.

Task T-36 (ORNL), the 4th line item, on risk assessment, should be completed ~

by mid-September. The staff responded to two questions on milestones in Fig. 2, 1987-1988 Proposed Schedule (Ref. 1). The first question. involved the NRC independent' audit review of the TER. The staff explained that this was an NRC quality assurrance process under the guidance'of the Technical Specifications Branch. The second question was on the definition of the milestone activity calling for the PSC to certify that the final TS~ proposal conform with the FSAR.

The staff stated that PSC should summarize the process used to assure correctness to final TS proposals.

PSC provided a preliminary response to:the NRC's proposed schedule in terms of a worst case estimate. .PSC stated that they would meet 8/30/87 milestone on the PSC response to Section 3/4.8 comments. However, PSC saw an overall 4 month slippage in the proposed schedule, as shown in Fig. 1. The slippage involves two milestones. On the 5/30/86 Comments, PSC projected the response to RAIs changing from 9/1/87 to 1/15/88. On the Cooling Function Comments,PSC PSC projected the response to comments changing from 7/15/87 to 11/1/87.

stated that these slippages may cause the release of the TS to PSC to be delayed from 5/88 to 8/88. However, PSC stated that there was sufficient time to implement the upgrade TS prior to plant restart from the fourth refueling.

This can be done by working on the various activities in parallel, rather that sequentially.

It is PSC's stated objective to use the upgraded Technical Specifications for operations following the fourth reactor refueling cycle. This activity appears to be slipping to a 12/1/88 plant shutdown and 1/30/89 plant startup. The refueling schedule calls for a shutdown of 61 days. This estimate may increase as a result of planning for specific activities. But, if the shutdown period exceeds 90 days, operating FSV will no longer be economical. The staff asked PSC for a letter officially providing comments and confirmation of this i~

schedule. The staff also requested that PSC consider submitting partial '

packages to minimize the effect of the slippages. 4 Other items highlighted during the meeting:

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1. PSC provided NRC with a draft of a parallel activity to the TSUP, the PPS-Setpoint Overview. The draft information is included herein as Enclosure 6.

2. PSC will develop a new proposal for the Inservice Inspection for Helium Circulators. This will be done as a separate licensing action, outside the TSUP.

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3. :PSC acce;.ed an action item to provide NRC with a report in 6 months to clarifj what. interlocks are defeated by the Interlock Sequence

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Switch as a result of a change in the position of the mode switch.

9 The area :f NRC, interest was directed to changes for startup and low power ope *ation.

4. 'Throughca; the discussion, PSC indicated the possibility of moving various items from the TS to the Fire Protection Plan. The staff requestet that PSC should highlight those TSs in this category .and clarify I'eir current position.

5. The staff briefly described the status of the DBA-2 study by ORNL.

As Soon as a draft copy of the study is available, the staff t ill 1 place a copy irto the POR and send a copy to PSC.

6. The staff and their consultant ORNL,~ recommended that PSC consider

-a requirement that during power operation one of the 12.5% condensate pumps be operable. This would provide additional assurance that FSV would avoid' fuel damage in the event of a loss of off-site power.

7. The staff requested that PSC submit a draft of their quality assurance process for the TSUP. This draft'will be reviewed with the TS Branch for the adequacy of the PSC approach.

KennethL._Heitner,ProjectorManager Project Directorate-IV Division of Reactors Projects - III IV, V and Special Projects enclosures:

As stated cc w/ enclosures: j See next page l-