L-76-159, St. Lucie Units 1 - Proposed Amendment to Facility Operating License DPR-67. Proposed Change to Technical Specification 3.1.1.5 with Regard to Deletion of Special Testing Exception Pertaining to Control Rod

St. Lucie Units 1 - Proposed Amendment to Facility Operating License DPR-67. Proposed Change to Technical Specification 3.1.1.5 with Regard to Deletion of Special Testing Exception Pertaining to Control Rod

ML18096B520
Person / Time
Site:	Saint Lucie
Issue date:	04/16/1976
From:	Uhrig R E Florida Power & Light Co
To:	Stello V Office of Nuclear Reactor Regulation
References
L-76-159
Download: ML18096B520 (11)

Text

.NRC FORM.~95 I2 76)U.S.NUCLEAR REGULATORY C ISSION NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL DOCKET NUMBER o-BBQ FILE NUMBER TO: 'r S tello IQLETTER CDOR IG INAL C3copv DESCRIPTION QNOTORIZED CSUNCLASSIFIED PROP Florida Pwr&Light Co Miami, Fla R E Uhrig, INPUT FORM ENCLOSURE DATE OF DOCUMENT 4-16-76 DATE RECEIVED 4-lv-7e NUMBER OF COPIES RECEIVED f 3 signed Ltr notarized 3-16-76....trans the following:

Amdt to OL/Change to tech" specs with regard tq deleti'on of+ecial testing exception pertaining to control rod withdrawl........

IrACymOWKEDGED

" (43 cys encl rec'd)~~6 Kgx REM~PLANT NAME: St Lucie fP1 SAFETY ASSIGNED AD: FOR ACTION/INFORMATION ASSIGNED AD..ENVXRO 4-20-76 e BRANCH CHIEF: PROJECT MANAGER;LXC~SSTo: c.ma rga 5 5 mes BRANCH CHIEF~PROJECT MANAGER;LIC~ASST, REG FILE NRC PDR I&E z7 GOSSICK&STAFF ASE EN NEER KNXGHT SIHWEXL INTERNAL D ISTRI BUTION BENAROYA IPPOLITO OPERATING REACTORS STELLO ERNST ALLARD SPANGLER SITE TECH GAMMILL STEPP PROJECT MANAGEMENT BOYD P, COLLINS HOUSTON PETERSON MELTZ HELTE>IES SKOVHOLT LPD~4 (~s.c, a TXC NS ASLB PAWLICKX REACTOR SAFETY ROSS NOVAK ROSZTOCZY CHECK AT&I SALTZHAN RUTBERG EXTERNAL DISTRIBUTION NATL LAB REG, V"IE LA PDR CONSULTANTS s OPERATING TECH EISENHUT SHAO BAER SCHWENCER GRIIIES SITE SAFETY&ENV ANALYSXS DENTON&MULLER BROOKHAVEN NATL LAB ULRIKSON(ORNL)

HULMAN SITE ANALYSIS VOLL1IER BUNCH J, COLLINS KREGER CONTROL NUMBER

~~~~~~\~~~~'E P.O.BOX 013100, MIAMI, FLORIDA 33101~gy9Vlz DOgf EIED 0lIc g'LG FLORIDA POWER&LIGHT COMPANY April 16, 1976 L-76-159 0 5 I ggll>Director of Nuclear Reactor e uk'on'v Attention:

Mr'.Vincent Stello, r., Director Division of Operating Reactors U.S.Nuclear Regulatory Commission Washington, D.C.20555

Dear Mr.Stello:

Re: St.Lucie Unit 1 Docket No.50-335 Proposed Amendment to Facility 0 eratin License DPR-67 V i>>/".</~%~~9)97~~~llouu'll COII11~1~~gglklll 8//In accordance with 10 CFR 50.30, Florida Power and Light Company submits herewith three (3)signed originals and forty (40)con-formed copies of a request, to amend Facility Operating License DPR-67.The proposed change is as described below and as shown in the accompanying technical specification page bearing the date of this letter in the lower right hand corner.This submittal proposes deleting the special test exception from Technical Specification 3.1.1.5 which would in effect prohibit the reactor from being critical below 515'F at any time.We also propose that condition A3 to Enclosure 1 of the operating license be deleted.These amendments are requested because difficulty has been experienced in withdrawing CEDM 44 at cold conditions.

During cold rod drop time testing, it, was determined that CEDM 44 was the second fastest rod., The cold rod drop time test procedure calls for the fastest and second fastest rods to be extensively tested.In lieu of this requirement, we have performed these same extensive tests on the fastest and third fastest CEDM's with satisfactory results.We propose to drop time test CEDM 44 10 times at hot full flow conditions and in addition plan to repair the CEDM at the next extended reactor shutdown which would be expected to last at, least 2 weeks.HELPING BUILD FLORIDA

~I'I Director of Nuclear Reactor Regulation Attention:

Mr.Vincent Stello, Jr., Director Page Two April 16, 1976 The proposed amendment has been reviewed and the conclusion reached that it does not involve a significant hazards considera-tion, therefore, prenoticing pursuant to 10 CFR 2.105 should not be required.Very truly yours, Robert E.Uhrig Vice President GEL/cpc Attachment cc: Mr.Norman C.Moseley Jack R.Newman, Esquire 0~~'E J STATE OF FLORIDA))SS COUNTY OF DADE)Robert E.Uhrig, being first.duly sworn, deposes and says: That he is a Vice President of Florida Power&Light Company, the Licensee herein;That he has executed the foregoing document;that the statements made in this said document are true and correct to the best of his knowledge, information and belief;and that he is authorized to execute the document on behalf of said Licensee.Robert E.Uhrig this Subscribed and sworn to before me day of 1976 Notary public, in and for the County of Dade, State of Florida NOTARV FURIIC STATE OF RORIDA AT I A>SE IILY COMPhlSSION EXPIRES JAN.26'%XI My commission expires: ENDED THRU Gth'-INsURANcE UNDfRWRITERS q~~0~REACTIVITY CONTROL SYSTEMS MIAIHUM TEMPERATURE FOR CRITICALITY LIMITING CONOITION FOR OPERATION 3.1.1.5 The Reactor Coolant System lowest operating loop temperature (T v)shall be>515'F when the reactor is critical.APPLICABILITY:

MOOES 1 and 2~8.ACTION: with a Reactor Coolant System operating loop temperature (T)<515'F, restore Tto within its limit within 15 minutes or be in PIT STANOBY within th5 3ext 15 minutes.SURVEILLANCE RE UIREHENTS 4.1.1.5 The Reactor Coolant System temperature (T)shall be determined to be>515'F.avg t~~a t b.Within 15 minutes'prior to achieving reactor criticality, and At least once per 30 minutes when the reactor is critical and the Reactor Coolant System temperature (T)is (525'F.avg Msth K>1.0.Q, ST.LUCIE-UNIT 1 3/4 1-7~AP>II 16 1976 I">L~ise&A~ca t r.(',4','"..."<<,jL"J>>'

~~SAFETY EVALUATION The Regulatory Position C.l of Regulatory Guide 1.68 discusses cold and hot rod drop testing of pressurized water reactors.The regulatory position recognizes that cold rod tests are per-formed to provide reasonable assurance that the hot tests will be successful.

An additional concern that would indicate the desirability of conducting cold rod drop time tests is that at some point in time, consideration may be given to the use of nuclear heat at low temperatures to expedite the heatup of the reactor coolant system.The Technical Specifications for St.Lucie No.1 permit criticality below 515'F under certain test conditions.

The position of Regulatory Guide 1.68 has been addressed by the successful completion of hot rod drop time tests.Criticality below 515'F has been prohibited by removing the special test exception from the Technical Specifications.

Additional testing of the CEDE will demonstrate that the ability to effectively shutdown the reactor has not been impaired.Therefore we have determined that the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the Safety Analysis Report has not been increased; that the probability for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report has not been created;and that the margin to safety as defined in the bases for the Technical Specifications has not been reduced.

~~E 1 I',~J