L-82-238, Forwards Responses to Questions 2-5 Re Overpressure Mitigating Sys,Per 820412 Request.Testing Procedures Verifying Operability Will Be Developed by 820801.Response to Question 1 Will Be Provided by 820716
| ML17212B671 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/07/1982 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Clark R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17212B672 | List: |
| References | |
| L-82-238, NUDOCS 8206140164 | |
| Download: ML17212B671 (8) | |
Text
REGULATOF, INFORMATION DI'STRIBUTION TEM (RIDS)
AOCESSION NBR:82061<l0164 DOC ~ DATE: 82/06/07
. NOTARIZED:
NO FACIL:50"335 St. Lucie Plant~
Uniit 1~ Florida Power 8 Light Co.
'AUTH~ NAME AUTHOR 'AFFILIATION UHRI6 g R. E, Flor ida 'Power 8 Li'ght Co ~
>RBC IP, NAME RECIPIENT AFFILIATION CLARKiR ~ AD Operating Reactors Branch 3
DOCKET 05000335
SUBJECT:
Forwards responses,to Questions 2-5 re overpressure miitigating sysiper 82041'2 request.Testin'g procedures verifing operabili;ty will be developed by 820801Response to Question 1 will be provided by 820716, DISTRIBUTION CODE:
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FLORIDAPOWER & LIGHTCOMPANY June 7, 1982 L-82-238 Office of Nuclear Reactor Regulation Attention:
Mr. Robert A. Clark, Chief Operating Reactors Branch g3 Division of Licensing U.
S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Clark:
Re:
St. Lucie Unit 1
Docket No. 50-335 Over ressure Miti atin S stem Florida Power 8 Light has reviewed your letter dated April 12, 1982, which requested additional information on the St.
Lucie Unit 1 Over pressure Mitigating System.
Your first question postulated a single failure event concerning the Power Operated Relief Valves.
We have not yet completed our evaluation of this event.
We expect to pr ovide a response on this question by July 16, 1982.
Responses to your remaining questions are included in the attachment to this letter.
Also attached is a corrected page from our letter (L-78-223) dated June 29, 1978.
The correction clarifies that the operator is to verify that PORV isolation valves are open instead of verifying that they are to open.
Very truly yours, Robert E. Uhrig Vice President Advanced Systems 8 Technology REU/PLP/cab cc:
J.
P. O'Reilly, Region II Harold F.
Rei s, Esquire
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ATTACHMENT Re:
St.
Luci e Unit 1
Docket No. 50-335 Over ressure Miti atin S stem uestion 2
Item 4 of Branch Technical
- Position, RSB 5-2, requires the OMS be tested to assure operability prior to each shutdown.
a.
Is this testing being performed prior to each shutdown?
b.
How are the OMS -setpoints verified prior to shutdown and reverified monthly while RCS temperature is (275'F?
~Res onse a.
Testing is being conducted as described in our June 29, 1978 letter (L-78-223).
We will develop procedures to verify operability prior to shutdown (prior to lowering temperature to 275')
by August 1, 1982.
b.
A procedure will be developed as noted above.
This test will be conducted prior to OMS use during shutdown and prior to use during the subsequent startup but will not be done more often than once every 30 days.
We do not intend to conduct the test while the OMS is in operation.
This may postpone the testing schedule on occasion.
The staff requirement that a report be submitted to NRC of all OMS (PORVs or SCS safety valve) operations to relieve pressure transients in the RCS is not included in your technical specifications as amended by your letter of April 13, 1978.
Address this requirement.
~Res onse The overpressure mitigating system (OMS) for St. Lucie Unit 1 uses the pressurizer Power Operated Relief Valves (PORV's) as the pressure relief mechanism.
FPL reports all challenges to the PORV's to the NRC as required by Item II.k.3.3.d. of the NRC letter dated May 7, 1980 (five Additional TMI-2 Related Requirements for Operating Reactors).
We committed to comply with this reporting requirement in our letter (L-80-184) dated June 13, 1980.
We have recently received an NRC letter dated April 6, 1982 which stated that, based on our response, TMI Item II.k.3.3. was resolved for St. Lucie Unit 1.
The NRC letter also added that ther e would be a future NRC request to incorporate these reporting requirements into the Technical Specifications.
Because we cur rently report PORV challenges as required, and because this item will be the subject of a future NRC request, we intend to defer action on proposing Technical Specifications until the TMI Action Plan Item request is made.
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4 In your letter of February 28, 1977, you stated that all of your operators will have completed a review of caus'es of past overpressure transients by April 8, 1977.
a.
What overpressure protection training have you performed since mid-1977?
b.
How do you ensure a continued emphasis is placed on possible overpressurization situations in your licensing and retraining progr ams?
c.
How is this training and LER review documented?
~Res onse All plant originated Licensee Event Reports and Operating Experience Feedback Reports are distributed to licensed operators for review.
These reviews are documented.
Over pressure transients and associated protective systems are included as an integral part of the replacement operator trai ning program.
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