ML20247H275
| ML20247H275 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/21/1989 |
| From: | Silver H Office of Nuclear Reactor Regulation |
| To: | Wilgus W FLORIDA POWER CORP. |
| References | |
| TAC-67801, NUDOCS 8907280331 | |
| Download: ML20247H275 (4) | |
Text
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' NUCLEAR REGULATORY. COMMISSION t
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Docket No. 50-302
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Mr. W. S. _Wilgus -
Vice President, Nuclear Operations Florida Power Corporation ATTN: LManager, Nuclear Operations
. Licensing F
P. O. Box 219-NA-21 Crystal River, Florida 32629
Dear Mr. Wilgus:
SUBJECT:
CRYSTAL RIVER UNIT 3 - ADDITIONAL INFORMATION ON EDG UPGRADE PROGRAM (TACH 0;67801)
Reference:
(1)' Letter from Rolf C. Widell dated April 27, 1989 regarding
. Diesel Generator Capacity Upgrade (2) Letter from Rolf'C. Widell dated September 15,19E0 regarding Long Term Emergency Diesel Generator Loading.
By letter dated April E7,1989,-(Reference 1) Florida: Power Corporation (FPC) submitted a schedule for upgrading the Emergency Diesel Generators (EDGs), an update of the status of the testina, and the. comparison reviews of IEEE Standard 387 against.the proposed EDG requalification program.
The present schedule is.to complete the modification of the EDCs during the-next re-fueling outage, in the spring of 1990.
In' order that we may complete our review, there are some areas of concern we would like you to address. Those areas are detailed in the following paragraphs.
You : stated that you have completed load testing at 3500kW.
It is not clear from your. letter which unit was tested at 3500kW and for what period of time.
The update is brief and did not convey sufficient new information to allow the staff to arrive at any technical conclusions regarding overall adequacy of the te sti ng.-
There is still some uncertainty about the automatically connected load. We request that you verify the' total automatically connected load and compare this load to the EDG rating. Furthermore, we request that you compare the increased continuous rating to the estimated EDG long-term load.
The FPC conclusion "...that testing of the EDG per IEEE Standard 387should not be performed..." is not in accordance with the IEEE Standard which was endorsed by NRC in Regulatory Guide (R.G.1.9).
The staff is willing to reconsider 5
certain requirements and the nurrber of tests (starts) to accommodate the avail-able time for testing during a refueling outage.
In addition, the proposed recualificatiun of the EDGs by "...either test of identical components, analysis or engineering judgement..."'does not replace an integrated test to requalify the upgraded EDGs at Crystal River 3.
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' P,r. W. S. Wilgus July. 21,1989 p
4 The staf.f ' requests-that th'e following items be submitted for our review:
a). A' list of the components which are to be requalified by testing.
1.
.b) A list of the components which are to be requalified by analysis, c) : A list of the components which are to be requalified by engineering
. ju dgement.
2.
Describe the expertise of those who' will do the' requalification' by.
engineering judgement, and provide the documented basis on which the.
requalification will be decided.
State' the time period allocated during shutdown for testing of the 3..
fully. modified machine and state how many start-stop tests will be made.to requalify the.EDGs.
4.
Your acceptance criteria, based on R.G.1.9 (IEEE STD-387) and FPC Technical; Specifications.
,ln' addition, by letter ' dated September 15,1988,.'(Reference 2), FPC submitted a summary of a study undertaken to evaluate the expected EDG loading.
Although we have previously~ discussed these-matters, we' request that you provide the
- following information:
1.
Tables 1 thru 4 of the attachment to Reference 2 tabulate the "A"-
and "B" EDG's 30 minutes-to-7-day extended time loads, including both the a' automatically and the manually applied. loads.
Submit sample calculations for the largest loads from each of these tables showing how these' loads were. derived, i.e., measured values that were extra-polated to reflect.the actual LOCA spectrum of parameters,. calculations only, equipment rated. nameplate data for the expected environmental conditions, etc.
Because of the lack of design margins and conservatism,
.the staff must establish, very accurately, the. actual. EDG loacing expected for the worst case LOCA condition.
2.
In Paragraph 4 of the attachment it is stated that " Failure of the Steam Driven Feedwater Pump (EFP-2) results in sharing of loads between "A" and "B" EDG's...." Further, you stated that "...the "B" EDG failure will bour.d all scenarios for the "A" EDG loading >rojected for seven days...." Explain which loads are shared and how t1ey can be shared if the "B" EDG fails. Also, submit'the following documents relating to EFP-2:
1.
P&ID's 2.
Electrical Schematics 1
3.
Operating Procedures for ESF loads 4
Test procedures to verify load sharing as a result of an EDG failure.
4 1
Mr. W. S. Wilgus July 21, 1989 3.
Describe in detail the electrical system EDG modifications planned for refueling outage VII.
We request your response to the above items by August 4,1989.
The reporting and/or recordkeeping requirements contained an this letter affect I
fewer than 10 respondents; therefore, OMB clearance is not required under l
P.L.96-511.
If you have any questions, please contact me.
Sincerely, Original signed by Harley Silver, Project Manager Project Directorate II-2 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation cc:
See next page l
DISTRIBUTION,
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- lir. W. S. Wilgus Crystal River Unit No. 3 Nuclear Florida Power Corporation Generating Plant cc:
Mr. A. H. Stephens State Planning and Development General Counsel Clearinghouse Florida Pcwer Corporation Office of Planning and Budget MAC - A5D Executive Office of the Governor P. O. Box 14042 The Capitol Building St. Petersburg, Florida 33733 Tallahassee, Florida 32301 fir. P. F. McKee, Director Chairman liuclear Plant Operations Board of County Commissioners Florida Power Corporation Citrus County P. O. Box 219-NA-2C 110 North Apopka Avenue Crystal River, Florida 32629 Inverness, Florida 32650 lir. Robert B. Borsum fir. Rolf C. Widell, Director Babcock & Wilcox Nuclear Operations Site Support j
Nuclear Power Generation Division Florida Power Corporation 1700 Rockville Pike, Suite 525 P.O. Box 219-NA-2I Rockville, Maryland 20852 Crystal River, Florida 32629 Resident Inspector fir. Gary L. Boldt U.S. Nuclear Regulatory Commissicn Vice President, Nuclear Production 15760 West Powerline Street Florida Power Corporation Crystal River, Florida 32629 P. C. Box 219-SA-2C Crystal River, Florida 32629 Regional Administrator, Region II U.S. Nuclear Pegulatory Commission 101 Marietta Street N.W., Suite 2900 Atlante, Georgia 30323 Mr. Jacob Daniel Nash Office of Radiation Control Departn.ent of Health and Rehabilitative Services 1317 Winewood Blvd.
Tallahassee, Florida 32399-0700
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Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Attorney General Department of Legal Affairs i
The Capitol Tallahassee, Florida 32304 l
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