ML20085L177
| ML20085L177 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 10/10/1991 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20085L180 | List: |
| References | |
| GL-91-01, GL-91-1, NLR-N91131, NUDOCS 9111010245 | |
| Download: ML20085L177 (6) | |
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W!Q E+@? % f( O ceanc am ou con,am Stanley hBruna P#c Wee Donc md (m Cm pe,-
r O Ba 2% Hanca.a Ondge_ tu Ce0Je em WMO
.e r,es y i u t om n OCT 10 WJ1 NLR-N9113'1 LCR 91-08 i
United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
LICENSE AMENDMENT APPLICATION REMOVAL OF VESSEL MATERIAL WITHDRAWAL SCHEDULE GENERIC LEl'TER 91-01 HOPE CREEK GENERATING STATION FACILITY OP" RATING LICENSE NPF-57 DOCKET NO. 50-354 This letter submits an application for amendment to Appendix A of Facility Operating License NPF-57 for the Hope Creek Generating Station and is being filed in accordance with the provisions of 10CFR50.90.
This amendment application proposes changes to Technical Specification (TS) 3/4.4.6, " Pressure / Temperature Limits", and its associated Bases in accordance with the guidance contained in Generic Letter 91-01, " Removal of the Schedule for Withdrawal of Foactor Vessel Material Specimens from Technical Specifications.
Specifically, Table 4.4.6.1.3-1,
" Reactor Vessel Material Surveillance Program - Withdrawal Schedule", is being removed, and references to the table in TS 3/4.4.6 and the associated Bases are being deleted.
In addition to the Generic Letter 91-01 endorsed changes, an additional change to the Bases for TS 3/4.4.6 is being proposed to correct an editorial error. contains a detailed description of the proposed changes along with our 10CFR50.92 significant hazards consideration analysis.
Marked up TS pages showing the proposed changes are included as Attachment 2.
In accordance with 10CFR50.91(b) (1), a copy of this request has been sent to the State of New Jersey as indicated below.
Upon NRC approval, please issue a License Amendment which will be effective upon issuance and shall be implemented within 60 days of issuance.
This latitude permits appropriate procedural modifications necessary to implement the proposed changes.
9111010245 911010
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PDR ADOCK 05000354 P
i Document Control Desk 2
OCT 101991 NLR-N91131 Should you have any questions or comments on tais transmittal, do not hesitate to contact us.
Sincerely,
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jllIY f'"^~W Affidavit Attachments (2)
C Mr. Stephen Dembek Licensing Project Manager Mr. T.
P. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Divi-ion of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 I
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REF: NLR-N91131 LCR 91-08 4
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' STATE OF NEW JERSEY
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COUNTY OF SALEM
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Stanley LaBruna, being duly sworn according to law deposes and says:
- I am Vice President'- Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set concerning the forth in our letter dated
.00T 101991 HopeLCreek Generating Station, are true to the best of my knowledge,-information and belief.
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Subscribed-and Sworn to before me 4
day of' dkb 1993
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ATDOMENP 1 HOEOSED OIANCES 'IO DK2MICAL SFBCIFIC' TICNi A
UCBM ME!NDGNP AfPGCKr10N NIR-N91131 NiiNNAL OF Vmmt, NAHRIAL WrHERAHAL SOHIILE IIR 91-08 CHERIC IEPDR 91-01 10EE OEFJC GENERATDC STATICM FN'fLTTY CHRATING IJCD4SEE NIY-57 D00GT 30. 50-354 I.
nanc r-inticm of diarne On January 4,1991, the NRC issued Genaric Isttar 91-01, "Humaval of the Schedule for Withdrawal of Reactor Veseal Material Mpar imans fran Tactnical Specifications." 'Ihe purpose of Generic Istter 91-01 was to provide guidance to licenseee on preparation of a license amendment application to rm the Technical Specification ('IS) schedule for the withdrawal of reactor vessel material specimanc. 'Ibe Generic Ietter 91-01 guidance was followed in preparing this anwudmut application. In addition to the 9aneric letter endorsed charges, an editorial charge to correct an crror in the TS Bases is also inclu: led in this request. Each of the propcsed changes is described belcu.
1.
Table 4.4.6.1.3-1, " Reactor Waaal Material Surveillance Program -
WitMrawal Schedule", is being ruroved.
2.
Neference to the Table 4.4.6.1.3-1 in Surveillance Requirunent 4.4.6.1.3 is being remwed. Specifically, the phrase "in accordure with the scha3ule in Table 4. 4. 6.1. 3-1" is being deleted.
-3.
Reference to the Table 4.4.6.1.3-1 in the final paragraph of Bases Section 3/4.4.6 is beirq replaced with a reference to UfSAR Section 5.3.
Specifically, the phrase " Table 4.4.6.1.3-1 to assure ocmpliance with the requirements of Apperrlix H to 10 CFR Part 50" is being replaced with the phrase "UFSAR Sectico 5.3 and Appendix SA."
'Ihe Imiltiplier for the values of neutrun fluence gthe orpte of 4.
Bases Figure B 3/4 4.6-1 is being charged from 10 to 10 II.
Damarm for Charne
'Ihis charge -is being suhaitted to remove an unmaq requirement frun the L
'ISs and to correct an editorial error in the 'IS Bases.
III. Justifica*1an fir 01arno
'Ibe proposed charges are justified as follows:
Fage 1 of 3
Att0 chm:nt:1 NLR-N91131 Removal of Vessel Material Withdrawal Schedule LCR 91-08 A.
Generic Istter Endorsed Charnes l
The provisions of Section II.B.3 of 10 CFR 50 Apperzlix H require that any change to the vsmaal material withdrawal scbarhile be a@ roved by the NRC prior to inplosnentatics1. As a result, cmtrol of changes to the scbarhile by way of a 7S requirment duplicates the requirements of Appendix H.-
The NRC concluded in Generic letter 91-01 that, since changes to the schedule are controlled by Appendix H, reaval of the actwhile frun the 7Ss will not result in any loss of regulatory control.
Since no charges to the withdrawal schedule would be permitted by the prtposed ctanges, and sinos regulatory control would be maintained, the changes are purely administrative in naturu.
The generic letter requires that a licensee propoeirg to delete the wit' M sctwhile frun TSs rnmit to maintainity the NRC al: proved versa of the schedule in the UfSAR. Based on review of the Hope Creek UFSAR, it has been detsrmined that all of the inforetion contained in 7S Table 4.4.6.1.3-1 is already included in the UFSAR. The withdrawal rdadule is included cu Page 5.3-11 and Page SA-10 while the lead factors and vossal locations are contained on Page SA-9.
B.
Correction of Blitorial Error The mitiplier for the values of neutron fluerce on the ordinate of Bases Figure B 3/4 4.6-1 is in.muct. Since the prrv-3 change corrects an editorial error in the existing TS Bases, the change is purely administrative in nature.
.E Sianifiturit Hazards (bnsihratirwt Evaluatirn In acoc'Idance witn the requirements of 10CFR50.91 ard using the criteria of 10CFR50.92r a significant hazards consideration analysis has been coupleted for the proposed charges to the Hcpe Creek Generating Station Technical Specificaticm. As a result of this analynic, it has been ocncitded that the s uposed changes:
L Do not involve a significant increase in the pWility or cmsequences of an amiriarit previrumly evaluated.
The proposed changec runave an urecary ard redundant requirunent l
frun the 7Ss and correct an editorial error in the TS Basea. These changes are purely administrative in nature. No charges to the vessel material surveillance pugme would be permitted as a result of these charry;. The surveillance program would continue to be inplemented in accordance with applicable regulations (10 CFR 50 Apperdix H) ard regulatory control of the program would be maintained. The changes would in no way inpact or alter the configuratico or operation cf the facility and would not affect any accident initiators or accident analysis a = $ 1ons. As a result, the propoo-1 charge would not L
significantly increase the probability or consegtmices of an ao:ident previously evaluated.
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1 Attcchrcnt 1 NLR-N91131 Removal'of Vessel Material Withdrawal Schedule LCR 91-08 2.
Do not create the possibility of a new or different kind of accidet fran any ami%t prevlausly evaluated.
The pW changes are purely achninistrative in nature. The chnges would allow regulatory control over the vnanal material surveillance pwgam to be maintained in amnnlance with the requirments of 10CFR50 Appendix H.
The changes would in no way inpact or alter the configuration or operation of the facility and no new modes of plant cperation would be created. As a result, the proposed chnge would not create the possibility of a new or different kind accident frun any accident previously evaluated.
Do not involve a si nificant rartr+ ion in a margin of safety.
3.
J Renoval of the redundant TS requirments and correction of the editorial error in the 1B Bases are considered administrative charges. These charges would not affect the material surveillance program and regulatory control over the program would be maintained thrugh the requiramnts of 10CFR50 Appendix H.
The changes would in no way impact or alter the configuration or cperation of the facility and would not affect any TS or safety limit. As a result, the proposed change would rot significantly reduce any margin of safety.
V.
Oanclusim As dimM in Item IV above, PSE&G has concluded that the proposed danps to the Technical Specifications do not involve a significant hazanis consideration iinae the changes (i) do not involve a significant irrrease in the probability or consequences of an axident previously evaluated, (ii) do not create the possibility of a new or different kind of accident frun any accident previously evaluated, and (iii) do not involve a significant reduction in a margin of safety.
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