ML20129J345

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Safety Evaluation Supporting Amends 155 & 147 to Licenses NPF-35 & NPF-52,respectively
ML20129J345
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 10/30/1996
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20129J333 List:
References
NUDOCS 9611060220
Download: ML20129J345 (4)


Text

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UNITED STATES g

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2065641001

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i SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION l

RELATED TO AMENDMENT NO.155 TO FACILITY OPERATING LICENSE NPF-35 AND AMENDMENT N0.147 TO FACILITY OPERATING LICENSE NPF-52 DUKE POWER COMPANY. ET AL.

CATAWBA NUCLEAR STATION. UNITS 1 AND 2 l

DOCKET NOS. 50-413 AND 50-414

1.0 INTRODUCTION

By letter dated December 14, 1995, as supplemented by letters dated May 16 and i

August 29, 1996, Duke Power Company, et al. (the licensee) proposed changes to the Catawba Nuclear Station, Units 1 and 2, Technical Specifications (TS) for diesel generators to incorporate guidance and recommendations contained in NRC Generic Letter (GL) 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation," GL 94-01, " Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators," NUREG-1431, " Revised Standard Technical Specifications for Westinghouse PWRs," and NUREG-1366, Improvements to Technical Specifications Surveillance Requirements."

The August 29, 1996, submittal provided additional information that did not change the scope of the December 14, 1995, application and the initial proposed no significant hazards consideration determination.

The NRC staff has previously completed a comprehensive examination of surveillance requirements (SRs) in plant TS that require testing at power.

The evaluation is documented in NUREG-1366, " Improvements to Technical Specifications Surveillance Requirements." The staff found that although most testing at power is important, safety can be improved, equipment degradation decreased, and an unnecessary burden on personnel resources eliminated by reducing the amount of testing at power that is required by plants TS.

l Subsequently, the staff issued GL 93-05. Additionally, in response to the i

NRC's decision on SECY-93-044, Resolution of Generic Safety Issue B-56,

" Diesel Generator Reliability," the staff issued GL 94-01, " Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators."

In this GL, the staff recommended that the licensees be allowed to voluntarily adopt the accelerated testing provisions of the Improved Standard TS upon the implementation of the provisions of the " Maintenance Rule" for the emergency diesel generators (EDGs), including the applicable i

regulatory guidance, which will provide a program to ensure EDG performance.

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Duke Power Company proposed to modify the Catawba Units 1 and 2 TS to 4

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2 incorporate recommendations and guidance in the above GLs. Additionally, Duke i

Power Company will be using guidance in NUREG-1431, " Revised Standard Technical Specifications for Westinghouse PWRs," in its effort to improve the Catawba TS.

2.0 EVALUATION The proposed changes to the Catawba TS are being made to improve the current TS action statements and surveillance requirements for the EDGs at Catawba Units 1 and 2.

The following changes will incorporate the guidance and recommendations contained in the above GLs.

2.1 Propose TS Chanaes Duke Power Company proposed the following additions and deletions to Catawba TS Section 3/4.8.1 "A.C. Sources." The strikeouts represent the deletions and the shaded text represents the additions or replacements:

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Limitina Condition for Operation 3.8.1.1. Action Statement a.

With an offsite circuit of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A&

S:;r : ~(hiuquiiFsdisffiithicifbsit by performing Surveillance Requirement 4.8.1.1.1.a w~ithin 1 h~our and at);least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.

If eith:r di:::1 ;:::r:ter: h:: n:t b::n ::::::: fully te:ted within th:

p::t 24 h:;r:, d:::n:tr:te it: 0"E"^"!LITY by perf: :ing Surveill::::

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":;;ir::::t 4.e.1.1.2.:.4 : d 4.e.1.1.2.:.5 with 24 hear: cal::: thi:

=rxill== r:;;ir: :t = ;=Sm:d within th: pr=t=: M h=r:.

Restore the offsite circuit to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

The above changes are consistent with the following recommendations in GL 93-05:

with the offsite circuit of the above required A.C. electrical power sources inoperable...

(Delete the following requirement to test EDGs: If either generator has not been successfully tested within the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, demonstrate the operability by performing Surveillance Requirement 4.8.1.1.2.a.5 and 4.8.1.1.2.a.6 for each such diesel generator, separately, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.)

Additionally, the wording "A.C. Sources" will be replaced by " required offsite source." This is being done because there will no longer be a requirement to test the remaining EDGs for this action statement; the only A.C. source to test would be the remaining offsite circuit.

Therefore, this is considered to be an administrative change.

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timitina Condition for Operation 3.8.1.1. Action Statement b.

b.

With one offsite circuit and one diesel generator of the above ACTION 7E),A.C. electrical power sources inoperableF'n(dT.f.7EFn required sisdirsfeEt3 demonstratetheOPERABILITYoftheremai$I i

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{piigsiFedibffsitsisiph"ditJ by performing Specification 4.8.1.1.1.a j

withih 1"h6di'~ind~'itTeist once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. If ; dic::1 g:::r:ter b:::::: in:p:r:ble d;; t: :ny ::::: Oth_ r th:n prepl:nned i

i prev:nt:tiv: ::inten:ne: Or te: ting, demonstrate

Requirements 4.8.1.1.2a.4) and 4.8.1.1.2a.5) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />

  • enle::

thedit::1g:n:r:terh::i::n:::::::fulQt:tedwithi: t5: ::t 24 h:tr:. sF3efiffliy?lsiffilhlf8?h6dFiittist nodistihtillTdsiiilos?idds f(Mdfi3fosthaltensinlydieh'lsdists{'Ithin 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or b j

Resteriit~1 east"ois'e~of the

' inoperable sources t'6 OP;RABLE itatus w l

l least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. P,::ter: :t le::t tw Offsite circuit:

nd tw dit::1 g:ncr:ter: t: OPEPJ3LE :t:tu: within 72 h ur; frc i

the tim: cf initi:1 1;;; cr be in :t 1:::t HOT STANDBY within the next S h ;r: :nd in COLD SHUTOOWN within the followin-30 h:;r:.

j iiilthithsidisiel?pehiFitsFIFsitsfeditsE0PERABLEistitui7?f611bsiTACTION

'sh withitheioffsiteleirtuithfestbredito!0PERABLEi'statush ~ifo11he "

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  • ~CThiiFiEtio6':Tihat 'rsiistr'ed if the" inopeFability' of"the diesel' was 'dui

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to an inoperable support system, an independently testable component, completed regardless of when the inoperable diese;this actio preplanned testing or maintenance, If required,'

l, generator is restored to OPERABLE status,,The, provisions of Specification 3.0.2 are not app 1_icable.)

The above changes are consistent with the following recommendations in GL 93-05 and NUREG-1431:

...If the diesel generator became inoperable due to any cause other than an inoperable support system, an independently testable component, or preplanned preventative maintenance or testing, demonstrate the OPERABILITY of the remaining OPERABLE diesel generator by performing Surveillance Requirements 4.8.1.1.2.a.5 and 4.8.1.1.2.a.6 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, unless the absence of any potential common mode failure for the remaining diesel generator is demonstrated.

With one (required] offsite circuit inoperable MQ one [ required]

DG inoperable restore (required] offsite circuit to OPERABLE status in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> QB restore [ required] DG to OPERABLE status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The deletion of "A.C. Sources" and the addition of " required offsite source" is being done because there will no longer be a requirement to test the remaining EDGs for this action statement. Therefore, the only A.C. Source to test would be the remaining offsite circuit. Additionally, the licensee is

4 also proposing to delete, from the TS Bases, any reference to testing the remaining EDGs when an offsite source becomes unavailable. This is acceptable because this requirement has been eliminated from NUREG-1431, in accordance with the guidance and recommendations of GL 93-05.

Limitina Condition for Operation 3.8.1'.1. First Half of Action Statement c.

i ed. With a diesel generator of the above required A.C. electrical power sources inoperablerIE(sisolfefEBtb?ACT!0NR ' demonstrate the OPERABILITY of the A.C.^offsite"sou'rces by"p)erforming Surveillance l

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Remiirement 4.8.1.1.la within I hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; :nd unle:: the i=perdility Of the die: 1 =: d= to prepl:=:d it: ting er =inte==

demonstrate

  • the operability of the remaining diesel generator by performing Surveillance Requirements 4.8.1.1.2a.4 and 4.8.1.1.2a.5 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> *'(6'E veri fyiniswi thi nT 24%oufEthat?no.Tp6tenti alisoasiohi' mode 7 fail ureTfo E

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the remanningldieseliexistspestbridieser^5hneritors^ to~0PERABLE" l

stafss within~72 hodFs~oFbe in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

  • '~"7"This' action'is not' reg'uired'if the inoperability of the diesel'was'due
  • ~ "to an inoperable suppod system, an independently testable component, or preplanned testing or maintenance. ' If required, this action is to be _

completed regardless of when the inoperable diesel generator is restored to OPERABLE status. The provisions of Specification 3,0.2 are not applicable.)

The above changes are consistent with NUREG-1431 and the following recommendations in GL 93...If the diesel generator became inoperable due to any cause other than an inoperable support system, an independently testable component, or preplanned preventative maintenance or testi1g, demonstrate the OPERABILITY of the remaining OPERABLE diesel generator by performing Surveillance Requirements 4.8.1.1.2.a.5 and 4.8.1.1.2.a.6 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, unless the absence of any potential common mode failure for the remaining diesel generator is demonstrated.

Limitino Condition for Operation 3.8.1.1. Second Half of Action Statement c.

& With one diesel generator inoperable in addition to ACTION b.f6Fd

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l (if :ppli=ble) 2:=, verify that:

l 1.

All required systems, subsystems, trains, components and devices that depend on the remaining OPERABl: diesel generator as a source of emergency power are also OPERABLE, 4

AND 2.

When in MODE 1, 2, or 3 with a steam pressure greater than 900 psig, the steam-driven auxiliary feedwater pump is OPERABLE.