3F0797-25, Provides Addl Clarification & Info on Nrc'S SER That Accompanied Amend 152,requesting 18 to 24-month Fuel Cycle Extensions.Withdrawal of TS Changes Made in Util ,Requested.Commitments Made,Encl

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Provides Addl Clarification & Info on Nrc'S SER That Accompanied Amend 152,requesting 18 to 24-month Fuel Cycle Extensions.Withdrawal of TS Changes Made in Util ,Requested.Commitments Made,Encl
ML20149H633
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 07/21/1997
From: Grazio R
FLORIDA POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
3F0797-25, 3F797-25, NUDOCS 9707250090
Download: ML20149H633 (6)


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  • L5 L Ouly 21,1997 jpF0797-25 U. S. Nuclear Regulatory Comm!ssion Attention: Document Control Desk
Washington, DC 20555 0001

Subject:

Technical Specification Change Reque.st No. 202 and Arnendment No.152,18 to 24-Month Fuel Cycle Surveillance Extensions

-References; 1. FPC to NRC letter, 2F0595-01, dated May 31,1995 s

2. FPC to NRC letter,3F1195-25, dated November 28,1995
3. FPC to NRC lettor, 3F1295-20, dated December 21,1995
4. NRC to FPC letter, 3N0296-04, dated February 13,199'S e

Dear Sir:

,On .May 31, 1995, Florida Power Corporation (FPC) submitted Technical

- - Specification Change . Request No 202 for 24 month fuel cycle surveillance extensions;. Reference 1. Subsequently,l FPC submitted additional information in-support for this' request; References 2' and 3. The U.S. Nuclear Regulatory Commission '(NRC) Issued Amendment :No.152 to the Crystal River 3:(CR 3) .

j Opsrating L; cense; Reference 4.-

Tne purpose of this letter lis tof1) provide additional clarificatinn and information on the NRC's Safety;EvaluatiowReport (SER.) that accompanied Amendment No.152, m

' Nnd: 2) withdraw requested ;Tcchnical: Specification changes rnade in' Reference 1 sthdt were not related to.24 month fuel cycle surveillance extensions and were not Lissued with Amendmeni}10.'152. LThese requested changes will be eva'uated and, -

1 Ob. Il 4;7, yll appropriate, submitted'as en e <future Technical Specification Change.

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clarifications, L.and :l withdrawal. 'of! thesTechnical f.

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i, q,uestions r'egardhg this letter,(please contacf Di F. Kunsemiller, Manager," Nuclear? l

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I 1 4 xc:a Regional Adniinistrator,'Re0 an i 11.

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A ENRR. Project M_anager

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R S ' ( fOl& Nuclear Regidatory Commission im s 3F0797-26 ~ a (Pago 3 6f'6 ;

iL IAttachmanL1 a '

a- -1 List of Regulatory Commitments  :

1 l U ,

l.The.following table. identifies those actions committed to by Florida Power

g. , -Corporation in thisl document, . Any other actions.discussea in the s'ubmhtal
f represents intended or. planned actions by Florida Power Corporation. ' They Late described to the NRC fer the NRC's information and are not regulatory

. c'ommitmer'ts.' ' Plea.se notify ' the Manager,7 Nuclear Licensing of any.

s:. ' questions. regarding ithisL document or any' associated ' regulatory commitments.

i ID NUMBER COMMITMENT COMMITMENT DATE

[ Evaluation of drift data and the Re; occurring n'

impact of the increased surveillance commitment, c 3F0797-25.1 intervals will be -' completed within - 180 days 180 days after restart from a following.

refueling outage and any potential. restart from a revisions to calibration intervals or refueling 5 setpoints will be made during this outage.

- period.  !

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J , i Clarification of SER Information in CR-3 Amendment 152 - ,

1 t LAK-cost-is'suance review of the'SER identified threo areas where NRC's description .

cof: the instrume'ntation monitoring programs differed slightly from FPC's program-and from informatbn provided in Reference 1. JOn January 16, 1997, ' FPC. and .

NRC ' technical personnel discussed these differences and it' was agreed that the

folloviing clarifications and additionalinformation should be provided
11) SER Section_2J). " Evaluation" Page 3; "Additianolly, the safety system instrumentation sotpc'nts include manufacturer-tvovided 30-munth instrument drift' valuss, and if the -

drift term was not bounded by the axisting allowance, the surveillance

. interval remained at 18-months , per the existing Technical i V ' Specifications. "

1) Clarification:

The 30 month instrument drift values that were provided by the manufacturer were f used Lin the setpoint calculations to determine -the proper setpoints for the i 1 instruments. These manufacturer's drift values were also used in the calculations

? for determining as-found tolerances. Surveillance intervals were increased to 24 I

months, unless the historical drift data did not bound existing as-found tolerances.

If the historical data was not bounding, either 18 month surveillance intervals were retained in - the Technical Specifications and surveillance procedures, or the ,

setpoints were revised to accommodate the larger drift.

2) SEE..Section 2.0. " Evaluation" Page 3:

"The licensee has implemented a program to monitor the effects of a

. 24-month Calibration Cycle nn the instrument drift as specified in GL 91-04. The purpose of this monitoring program is to provide a means -

to: verify the assumptions made in the~ setpoint methodology with regard lta instrument' drifL The monitoring program also providas a  ;

rnethod to determine the adequacy of the instruments surveillance - l n intervals. "

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' (The instrument' Drift' Program is fan ongoing program .which: will;m'onitor future ~

, Je;urveillanc'e procedure as found and as-left data, and.wilfincorporate lnew data into - -

M *Jkdriftjstudyl spread sheets with the existing. drift data. The revised drift data'

% ears siandard ~ deviation,s 95%/90% tolerance intervals,. etc., will be . compared .

f Swith the existing drift data tb ensure the conclusions in the drift study remain valid. -

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L There"a're currentiv no plans to make' direct comparisons between the drift data'and terms. used in the setpoint caldulations~.

?) SER Section 2.0. "Evalugflon" Paae 3:

' "Th'e ^ ongoing ' monitoring program provides further assurance that unacceptable instruntent drift will be evaluated immediately and the

calibration l interval'and the Instrument setpoint' will bo revised to i

account for any additional drift."

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3) Clarif! cation:

. Drift data will'be taken crice every 2 years during refueling outages. Evaluation of >

[ s (tho' data and the impact oflthe increased surveillance interval will be completed withini180 ' days after restart and any potential revisions to calibration-intervals or 7

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setpoint'sl will be made~~during' this par;od. This' period for completing the drift  :

. evaluations' is- welli within the 18L month operating- experience' data for

instrumentation d/ift. '

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, ' :3F0797-25 i g ( Page 6 of 6

Attachment 3.  ;

, Withdrawal of Technical Specification Change Requests that are not Rela'ted to 24 .j

. . Month Fuel Cycle Surveillance Extensions  !

I F i In addition to. Technical Specitication Change Requests for 24 rnonth surveillance -l frequency extensions, Reference 1 also requested named Function changes. and changes to the Allowable Values for determining operational status for the Reactor

Coolant Pumps, . Main Turbino, Main Feedwater Pumps, and for Emergency

'Feedwater Initiation. A change for the Control Room Isolation High Radiation l setpoint from an allowable value to an approximate value was also requested in this

. submittal.- These requests,. as delineated below, are withdrawn and will be '

evaluated and resubmitted at a later date, if appropriate:

Withdrawal List Table 311-1 The FUNCTION name for " Reactor Coolant Pump Power Monitor (RCPPM)" is changed to " Reactor Coolant Pumps," and the ALLOWABLE VALUE is changed to "More than one pump tripped."

Iahle 3.3.1d The FUNCTION name for " Main Turbine Trip (Control Oil Pressure)"

-is changed to " Main Turbine," and the ALLOWABLE VALUE is changed to " Turbine Tripped."

s Table 3.3.1-1 The FUNCTION name for " Loss of Both Main Feedwater Pumps ,

(Control . . Oil Pressure)" is changed to " Main Feedwater Pumps," and the

. ALLOWABLE VALUE is changed to "Both Pumps Tripped."

Table 3.3.114 The FUNCTION 1.a name for "EFW Initiation - Loss of MFW Pumps -(Control Oil Pressure)" is changed to "EFW Initiation - Main Feedwater

- Pumps," and the ALLO.WABLE VALUE is changed to *Both Purnps Tripped." .

a The CHANNEL CAllBRATION'setpoint for " Control Room Isolation" SR 3.3.161 is changed from " Allowable Value less than or equal to two times background." to

, approximately two times background."

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