ML20085J663
| ML20085J663 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 10/17/1991 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20085J666 | List: |
| References | |
| NLR-N91150, NUDOCS 9110290301 | |
| Download: ML20085J663 (6) | |
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NLR-N91150 lle ference: LCR 91-12 J.S.
Nuclear Regulatory Cowmission Attention:
uc.cument Control Desk Washingten, DC 20555 Gentlemen:
REQUEST FOR AMENDMENT FACILITY OPERATING LICENSE NPF-57 HOPS CREEK GENERATING STATION DOCKET NO. 50-354 Public Service Electric and Gas Company (PSE&G) hereby transmits an application to amend Appendix A of Facility Operating License No. NPF-57 in accordance with 10CFR50.90.
This amendment request would revise Section 3/4.2.3, MINIMUM CRITICAL POWER RATIO of the Hope Creek Generating Station (HCGS) Technical Specifications.
A descripticn of the requested amendment, supporting information and analyses for the change, and the basis for a no significant hazards consideration determinntion are provided in Attachment 1.
The Technical Specification pages affected by the proposed change are marked-up in Attachment 2.
Pursuant to the requirements of 10CFRSO.91(b) (1), PSE&G has provided a copy or this amendment request to the State of New Jersey.
"pon NRC approval of this proposed change, PSE&G requests that the l
amendment bo made efinctive on the date of issuance, but j
2mplementable within sixty days to provide sufficient time for anacciated administrative activities.
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.I 7110240301 911017 r
PDR ADOCK 050003'54 i
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s OCT 1 L 1991
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Document Control Desk,
NLR-N91150 Should you have any questions regarding this request, we will be pleased to discuss them with you, j
Sincerely, f hfts; e --
' Attachments Affidavit C
Mr. T. T. Martin, Administrator USNRC Region I Mr.
S.
Dembek USNRC Licensing Project Manager Mr. T.
P. Johnson USNRC Senior Resident-Inspector Mr. K. Tosch, Chief, Bureau-of Nuclear Engineering New Jersey Department of Environmental Protection
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REF: ULR-N91150 STATE OF NIN JERSEY
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SS.
COUNTY OF SALEM
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Stanley IaBruna, being duly sworn according to law deposes and sayst I am Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated UCT 17 1991
, concerning the Hope Creek Generating Station, are true to the best of my knowledge, information and belief.
Wren
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Subscribed and Sworn to jb fore me this _
/7 day of 8ckh 1991 bl1kt/
0 A
Notary $ blic of/New\\ Jersey EUZABETH J. KIDD Notry Fudhc of New Jersey My ConwNssion Expires April 25.1095 Hy Commission expires on
Ecf: IJ,91-12 i
A'ITRIMN1' 1 HD14HD 'mC1NICAL slicinCAT1GE AND IRSIE Q{$33
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' PROPOSED C11ANGE TO TIIE TECIINICAL SPECIP7?ATIONS FACILITY OPEllATING LICENSE NPP-57 IlOPE CREEK GENERATING STATION DOCKET NO. 50-354 ref: IIR 91-12 7dISQtIPTICH OP 11IE OWG As shown on the unrked-up 7tdinical Specificatics ('IS) and BASES pagos in Attachmont 2, PSE&G requests that the constants in the equation for T B chalgod.
II.
IFKG lut Tile QWG In a letter, dated April 15, 1991, General Electric 02apany infonnod PSEGG that the cosctants in the equation for r,h, as speciflod in 'IS Section 3.2.3, had bem chargod. The ctanges were the ault of using a now aralytical method for the HOGS reload licensing calculation and amlied to Ibel cycles 2, 3, 4, and futuru cycles.
Tho twM dTarges in this ruquest will result in the 11 ops Crxek GeneratiIg Statica (liCES) TS calculation for 7 (relatirg to control rod scram inserticx1 times) being nore conservt.tive which, in turn, results in more conservative operatirq MINIlm QRITICAL POWER RATIO (MCPR).
m.
JWPIFICATICH EUt 1UE OWG Usirq the i equation ard data frun mntrol rod scram insertion time testirg, n
the value or r is calculated. h calculated r is then used to establish the operatint; limit MCFR. This limit is specified in the 03ru Operatlig Limits Report (CDIR). It is this operatirg limit MCIYt value that actual McPR nust be equal to or greater thar per TS 3.2.3.
As irdicated above, the i apation and data frun control rod scram insertion n
t3mo testirq are used in tho TS 3.2.3 equation to calculate the value of r.
For any value of r less than zero (nogative value), the operating limit HCFR is taken as a 111nimum number. At any positive i value point (on a graph in the 001R that plots the operating limit MCPR against r - for values of r betwoon zero and one), the cporatirg limit MCPR increases to a larger tuber. This increase is a penalty incurrcd for sic 5ur control rod irmrtion times. Tim calculated r values usirg the existing constants in 'IS were feutti to be always negative for cycles 2, 3, ard 4; herxm the operating limit MCIR was always the mininum value for thosa cycles. h valuca for 7, re-calculated using the tw constants provided by General Electric Campany for the same cycles, also remained rxgative. Since the new constants produced less negative values for 7, using thoca propoced constants will recult in a higher opcIntirq limit MCHR (peralty) - should the value for r ever boccro positive in future cperation.
_1 IV. 10CMt50.92 SIGGYIQMr HhEARIE Q1L7WRErIQi ANALYSIS PSEh4 has, pursuant to 100RSO.92, reviewed the propnami acendment to determine idiother our request involves a significant hazards considaraticn. We have-determined that:
- 1. h tw=ratitwt of Hma Creek GGneratira StatIrun fIM) in a 1=-daium with the
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mrnnnaad dianma will not involve a sianif f mnt incr =aa in the nrv4=hility or cremamannan of an amidant nrevin=1v evaluatg6
'Iha rurm 1 amendment will result in 'a more conearvative cperating limit K:FR.
It will not irvolve any physical ctiange in plant aminaant or in the way that the plant is operated and will,- therefore,- not increase the probiollity of any amidant or malfunction of equipnent important to safety previously evaluated in the Updated Final Safety Analysis Report (UFSAR). Should the calculated value for t' aver hanrna positive, the prtmwed ctiarge in cmstants will _ impose a'more consarvativo limit on MCPR than the current TS limits - wilicts would tend to decrease'the consequences of any m_11 dant or malfunction of equipment inportant to safety.
- 2. h -- 4ir=1 of Hma Craalr Geeratino Statim (HOCS) in 7- = = -amia-with the nrupcoed diange will not create the consibility of a nrE or differuit kird of Mfrom any nrevir==1v evaluated.
'Ihere are no physical-cfianges to the plant or to the manner in whicts the plant 1
is operated involved _in the proposed revision.
Ihe proposed ctiange will intrninna more conservatism into operating limit MGR values and in no way creates the potential-for any.new or different accident.
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' 3. 'the coeratirwn of Hnr= Crvxk Gmeratim Statimi W) in ammrtiarice w@ the proposed danaa dnaa not involve a sianificant rvvtwtion in a umtrin of anfety.
'Siry:e all the r values are negative usirs either the existirg or prgosed more conservative constants for calculating r for all cycles affected by the new ocostants,' the operating limit Minimum CEitical Power Ratio was not impacted during past operation nor for tha present cycle. 'Iherefore the p --W diange
- did not identify any decrease ir. uny margin of_ safety for past operation and
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L has the potential for increasirg the safety margin on operating limit MCPR for future plant operation.
I Conclusiczu l-Rama upon the foregoing evaluation, we have determined that this proposed
- rilange does rot involve a Significant Hnards Consideration.
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