L-76-326, Response to Letter of 8/13/1976 to Evaluate Reactor Coolant System Design and Provide Certain Information Regarding Susceptibility to Overpressurization Events, FP&L Will Report the Results by 10/15/1976

Response to Letter of 8/13/1976 to Evaluate Reactor Coolant System Design and Provide Certain Information Regarding Susceptibility to Overpressurization Events, FP&L Will Report the Results by 10/15/1976

ML18127B157
Person / Time
Site:	Saint Lucie
Issue date:	09/03/1976
From:	Robert E. Uhrig Florida Power & Light Co
To:	Ziemann D Office of Nuclear Reactor Regulation
References
L-76-326
Download: ML18127B157 (5)

Text

NRC FoRM 195 U.S. NUCLL'AR REGULATORY 'ISSION DOCKET NUMOER g 7al r

'0-335 FILE NUMBERS NRC DISTRIBUTION FoR PART 60 DOCI<ET MATERIAL RIb~ f TO: FROM: DATE OF DOCUI1ENT Florida Power & Light Company 9 3 76 Mr. Dennis L. Ziemann Miami, Florida DATE RECEIVED ABETTER Ifr. Robert E. Uhrig 10 22 76 0 NOTOR IZ E D PROP INPUT FORM NUMBER OF COPIFS RECEIVED 0 ORIGINAL. JRCUNC LASS IF I E D One signed copy

@SCOP Y DESCRIPTION ENCLOSURE Ltr. re our 8/13/76 ltr....furnishing requested information regarding Reactor ACKNOWLZDGED.

Vesspl Overpressurization.

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'iD050T REMPVE (2-P)

REACTOR VESSEL OVERPRESSURIZATION DISTRIBUTION PER G EECH 10-21-76 PLANT NAME:

St. Lucie ijl SAFETY FOR ACTION/INFORMATION 10 22 76 RJL BiiANCH CHIEr . 5 Ziemann LIC ~ ASST: Silver PROJECT MANAGER: Di s INTERNAL DISTRIBUTION NRC PDR

-GOSSICK & STAFF SHAO BUTLER ZECH EXTERNAL DISTR IOUTION ONTROL NUMOER LPDlh: F t. Pierce Fla NSIC. yu647 IBSEN~

Nflc FORM IOII I2 76)

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P. O. BQX jc 6g~~g ~gg V' Sc ~tember 3, 197; L-76-326 Office of nuclear Reactor Regulation Attention: Rr. Dennis L. Eiemann, Chief Operating Reactors Branch 02 Division of Operating Reactors U S. Nuclear Regulatory Comission Sashington, D. C. 20555 Dear Hx. Ziemann=

Re: St. Lucie Unit 1 Docket No. 50-335 Reactor Uessel Ove ressurization Your letter of August 13, 1976 requested that Florida Power a Light Company (PPL) evaluate the St. Lucie reactor coolant system design and provide certain information regarding the susceptibility to overpressurization events. You requested that we either provide the information within 60 days, or explain why we cannot taeet this schedule and provide a schedule that we will meet.

Xn response to your request, FPL has joined a utility tas3c group which was formed to examine the complexity of overpressurization events for the purpose of developing a solution to the over-pressurization problem. The task group wilX. meet in the near future to evaluate ways to minimize the potential for reactor vessel overpressurization events.

In addition, some revisions to the St. Xucie Unit 1 operating procedures have been made to reduce the probability of ovei-pressurization events. FPL will continue to examine the St.

Lucie operating procedures and administrative control.s during the 60 day period referenced in your letter to evaluate possible additional procedural changes which could further reduce the possibility of reactor vessel overpressurization. As an 9.nteri~

measure plant operating personnel have been directe8 to exercise caution, especially during operation at reduced pressure and temperature, in controlling primary systen pressure.

Office of Nuclear Reactor Regulation Attention: Ma. Dennis L- Ziemann, Chief Page Two Re vill report the results of task group meetings and FpL Procedure reviews by October l5, 1S76. Our recoumenQations and a schedule for providing the information you requested vi3.l be included in the report.

Very truly yours, Robert: E. Uhrig Vice President

,RBU/NAS/cpc cc. Hr. Nolan C. Hose).ey Jack R. Hevman, Esquire

V 'I t Y' fTVTD ova-ua-boa.aaz thh Al~l