ML17345B426
| ML17345B426 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 01/30/1984 |
| From: | Williams J FLORIDA POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| TASK-2.K.3.05, TASK-TM GL-83-10C, GL-83-10D, L-84-22, NUDOCS 8402030220 | |
| Download: ML17345B426 (8) | |
Text
REGULATORY FORMATION DISTRIBUTION S EM (RIDS)
ACCESSION NBR 8402030220 DOC ~ DAT'E 84/01/30 NOTAR'I'ZEP NO DOCKET
.FACIL:,50 280 ~Turkey -Point <<Pl anti,Unit"3>> Flor i.da <<Power and Li'ght C
05000250
'50 '251 Turkey Point Planti 'Unit 4i Flor ida 'Power'and Light C-05000251 AUTH'BYNAME AUTHOR AFFILIATION WILLIAMS'
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Flor,ida ~Power, 8,Li'ght Co,
'RECXP ~ NAME RECIPIENT AFFILIATION EISENHUT~D+G ~
Division of Licensing
SUBJECT:
Provides status of.planned responses to Generic Ltr 83 10D L 83 10Dire post TMI requirements concerning. automatic" trip of reactor coolant pumps (Item II~ K,3;5),'Program completion date revised to 840301
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+ling FLORIDA POWER 5 LIGHTCOMPANY January 30, 1984 L-84-22
,Office, of Nuclear Reactor Regulation Attention:
Mr. Darrell G. Eisenhut, Director Division of Licensing U. S.
Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Eisenhut:
Re:
Turkey Point Units 3
and 4
Docket Nos. 50-250 and 50-251 Post TMI Requirements-Automatic Trip of Reactor Coolant Pum s
Generic Letter 83-10d Our letter L-83-246, dated April 20, 1983, presented the plan for deiiionstr a-ting compli ance with the criteri a for resolution of TMI Action Pl an Item II.K.3.5 which were established in letters from Mr. Darrell G. Eisenhut of the Nuclear Regulatory Commission to al 1 Applicants and Licensees with Westinghouse designed Nuclear Steam Supply Systems (83-10c and d) dated February 8, 1983.
This letter presents the status of the planned responses to NRC Generic Letters83-10c and d; the date by which all parts of the program are to be completed has now been revised to March 1, 1984.
- However, a
submittal to parti ally fulfillthe requirements has been transmitted to you by WOG letter OG-110, dated December 1,
1983 (Sheppard to Mattson).
Section I of the attachment to NRC Letters83-10c and d is concerned with "Pump Operation Criteria Which Can Result in RCP Trip During Transients and Accidents."
Subsection 1 of Section I presents guidelines for establishing setpoi nts for RCP Trip.
The Westi nghouse Owners 'Group response to thi s.
section of NRC Letters83-10c and d is contained in Revision 1 to the Emergency
Response
Guidelines, which has been approved and issued.
Our letter L-83-237, dated April 15, 1983, committed Turkey Point Units 3 and 4
to the implementation of WOG Revision 1 to the Emergency
Response
Guidelines.
The Revision 1 material, expected to be issued in June 1983, arrived in mid-December 1983.
The executive volume and five volumes of supporting documen-tation have not yet been received.
Therefore a revised schedule to implement the Revision 1
ERGs is being prepared based on the assumption that all material is received from the WOG in January 1984.
The revised schedule tentatively calls for plant specific ERGs to be implemented at Turkey Point by December 31, 1985.
We will forward the schedule extension when finalized.
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Office of Nuclear Reactor Regul ation Attention:
Mr. Darrel-1 G. Eisenhut Page 2
The RCP Trip Criterion being adopted in the Turkey Point Units 3 and 4 specific-procedures not only assures RCP trip for all losses of primary coolant for which trip is considered necessary but also permits RCP operation to continue during
'ost non-LOCA accident including stean generator tube rupture events up to the design basis double-ended tube rupture.
The generic applicability of the RCP trip criterion selected has been documented by the Westinghouse Owners Group in "Evaluation of Alternate RCP Trip Criteri a", September 1983, which as stated above has been submitted to the NRC for review.
Subsection 2 of Section I of the attachment to NRC Letters83-10c and d provides guidance for justification of manual RCP trip.
Subsection 2a requires that compli ance with 10 CFR 50.46 be demonstrated in Appendix K small break LOCA analysis given that the RCPs are tripped 2 minutes after the onset of reactor conditions corresponding to the RCP trip setpoint.
Westinghouse has completed generic verification for the Westinghouse Owners Group that predicted LOCA transients presuming the 2 minute delved RCP trip are nearly identical to those presented in Safety Analysis Reports utilizing the WFLASH Evaluation Model.
Thus, the Safety Analysis Reports for all pl ants are a valid means to demonstrate,compliance with the Subsection 2A guidelines.
Westinghouse is now performing better estimate WFLASH analyses to demonstrate, generically, compliance with the guidelines presented in Subsection 2A of Section I of the attachment to NRC Generic Letters83-10c and d.
These analyses will identify the minimum time available for operator action for a range of break sizes such that the ECCS acceptance criteria of 10 CFR 50.46 are not exceeded.
It is expected that the minimum time available for operator action will exceed the value contained in N660.
Combined with the Subsection 2A justification.
This will justify manual RCP trip for all plants.
Turkey Point Units 3 and 4 will review the WOG reports upon receipt.
It is expected that the generic safety analysis report provided in the WOG report will bound the Turkey Point Plant.
FPL endorses the applicability study to be included in the WOG report concerning the acceptability of manual RCP trip criteri a.
The review of the report and the final technical justification for treatment of RCPs should be within one year following receipt of the WOG report.
0
Office of Nuclear'eactor Regul ation Attention:
Mr. Darrell G. Eisenhut Page 3
Cr The Westingliodse',Owners Group intends to submit the generic report justifying manual RCP trip by March 1, 1984.
This will complete the documentation comprising a generic reply to NRC Generic Letters83-10c and d.
Very truly yours, Vi ce President Nuclear Energy Department JWW/JEM/js Attachment cc:
Mr. Janes P. O'Reilly, Region II Harol d F.
Rei s, Esqui re P NS-LI-84-008
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