JPN-96-046, Forwards Addl Info Re 920612 Application for Amend to License DPR-59 Re Power Uprate,To Reflect Interposed Amend Issued,Update Ref to Rept on TS Pages & Change Rev Bars on Previous Update Pages
| ML20134M163 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/20/1996 |
| From: | William Cahill POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20134M167 | List: |
| References | |
| JPN-96-046, JPN-96-46, NUDOCS 9611220253 | |
| Download: ML20134M163 (4) | |
Text
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N 123 Main Streer White Plains, New York 10601 914-681 684('
914 287 3N9 (FAX)
- > NewYorkPbwer
& Authority November 20,1996
"""*") J CahiH, Jr.
Chief Nuclear OHicer United States Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, DC 20555
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 Supplemental Information Regarding Updated Page Changes for Proposed Change to the Technical Specifications Renardina Power Vorate (JPTS-91-025)
J
References:
See below.
Dear Sir:
The Authority submitted a proposed amendment (Reference 1) to the James A. FitzPatrick Technical Specifications (TS) to raise the authorized maximum power level to 2536 MW,.
This letter transmits TS changes to: (1) reflect an interposed amendment that was issued; (2) update references to reports on TS pages; and (3) change revision bars on previously submitted update pages which were erroneously positioned on the pages. Also included in this transmittal are statements regarding current analyses applicable to power uprate.
Affect of Interposing Amendments on JPTS-91-025 No Significant Hazards Determination Previous letters (References 2,3, and 4) transmitted TS page updates and Operating License (OL) page changes to the NRC. These changes incorporated amendments issued by the NRC since the Authority's original application, requests from the NRC staff associated with TS references and OL changes, and minor editorial changes.
The Authority has reviewed the changes proposed in this letter and in References 1 through 4 and has determined that these changes do not affect the bases or conclusions of the no significant hazards considerations described in the original application (Reference
- 1) or NEDC-32016P-1 (Reference 5). The changes provided in Attachment I are administrative in nature and support the conclusions presented in References 1 and 5.
Attachments 11 and ill provide descriptions of the page changes and a markup of the effected pages, respectively.
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l CE Power Upr:t3 S f::ty Analysis Reference 6, in part, provided clarifications regarding NEDC-32016P (Reference 7) in October 1996. NEDC-32016P-1, which superseded NEDC-32016P, was provided to the g
NRC, along with a request to return all copies of NEDC-32016P (See Reference 8) in August 1993. Copies of NEDC-32016P were returned to the Authority by the NRC (Reference 9) in January 1994. Reference 6 should have provided clarifications regarding j
NEDC-32016P-1. The Authority has reviewed the clarifications regarding NEDC-32016P and compared them to NEDC-32016P-1. The results of this review show that the Reference 6 clarifications are also applicable to NEDC-32016P-1.
Subsequent to requesting all copies of NEDC-32016P from the NRC, the Authority l
identified two errors in the original power uprate amendment application and informed the I
NRC under Reference 10. Specifically, the TS limits for vessel high pressure scram were inadvertently listed in a table of analyticallimits. Reference 10 provided an Errata sheet for NEDC-32016P. The same error was contained in NEDC-32016P-1 and was corrected under Reference 11. The corrections are shown in Attachment IV.
Radiological Effects of increased Power During a telephone conference on November 12,1996, the NRC staff requested calculations (Reference 12 through 15) of the radiologicalimpact of design basis accidents. The Authority mailed the requested information to the NRC on November 14, 1996.
Summary of Attachments Attachments I, ll, and lli are updated TS pages, description of the page changes, and a markup of the effected pages, respectively. Attachment IV provides corrections to NEDC-32016P-1.
There are no commitments made by the Authority in this submittal. If you have any questions, please contact Ms. C. D. Faison.
Very truly yours, q
William J.
ahill, Jr.
Chief Nuclear Officer
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4 Rsfrrzncis:
1.
NYPA Lettrr, R. E. Bardl3 to the NRC, (JPN-92-028), " Proposed i
Chang:s to the Technical Specificitions Ragarding Pow:r Uprate (JPTS-91-025)," dated June 12,1992 2.
NYPA Letter, M. J. Colomb to the NRC, (JAFP-96-0306), " Updated i
Page Changes for Proposed Change to the Technical Specifications l
Regarding Power Uprate (JPTS-91-025)," dated August 15,1996 l
3.
NYPA Letter, M. J. Colomb to the NRC, (JAFP-96-0426), " Submittal l
)
of Updated Pages Regarding Proposed Changes to the Technical Specifications Contained in the Referenced Letters," dated October 23,1996 4.
NYPA Letter, W. J. Cahill, Jr. to the NRC, (JPN-96 043), " Response to Request for Additional information Regarding Power Uprate," dated November 14,1996 5.
General Electric Report NEDC-32016P-1, " Power Uprate Safety Analysis for James A. FitzPatrick Nuclear Power Plant," April 1993 (proprietary), including Errata and Addenda Sheet No.1, dated January 1994 6.
NYPA Letter, M. J. Colomb to the NRC, (JAFP-96-0391),
" Supplemental Information Regarding Updated Page Changes fo>
Proposed Change to the Technical Gpecifications Regarding Power Uprate (JPTS-91-025)," dated October 3,1996 i
7.
General Electric Report NEDC-32016P, " Power Uprate Safety Analysis for the James A. FitzPatrick Nuclear Power Plant," dated' December 1991 j
8.
NYPA Letter, R. E. Beedle to the NRC, (JPN-93-060), " Proposed Changes to the Technical Specifications Regarding Power Uprate
)
(JPTS-91-025) Revision 1 to Safety Analysis NEDC-32016P," dated August 18,1993 9.
NRC letter,' John E. Menning to Ralph E. Beedle, " General Electric Proprietary Reports NEDC-31317P and NEDC-32016P (TAC NO.
M83182)," dated January 19,1994 10.
NYPA Letter, R. E. Beedle to the NRC, (JPN-93-089), " Response to NRC Request for Additional Information Power Uprate Submittal (TAC No. M83182)," dated December 29,1993 11.
General Electric Report NEDC-32016P-1, " Power Uprate Safety Analysis for James A. FitzPatrick Nuclear Power Plant," April 1993, Errata and Addenda Sheet No.1, January 1994 12.
James A. FitzPatrick Calculation, JAF-CALC-RAD-00007, Rev.1,
" Power Uprate Program - Onsite and Offsite Post-Accident Atmospheric Dispersion Factors," September 1995 13.
James A. FitzPatrick Calculation, JAF-CALC-RAD-00023, Rev. O,
" Power Uprate Program - Technical Support Center Post-Accident Radiological Habitability Study," August 1996
t 1
R-fzrances (cont'd) 14.
James A. FitzPatrick Calculation, JAF-CALC-RAD-OOO42, Rev. O,
" Control Room Radiological Habitability Under Power Uprate Conditions and CREVASS Reconfiguration," September 1995 15.
James A. FitzPatrick Calculation, JAF-CALC-RAD-00048, Rev. O,
" Power Uprate Project - Radiological Impact at Onsite and Offsite Outdoor Receptors Following Design-Basis Accidents," May 1996 Attachments: as. stated cc:
Regional Administrator U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Office of the Resident inspector U. S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 Ms. K. Cotton, Acting Project Manager Project Directorate 1-1 Division of Reactor Projects-l/il U. S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, DC 20555 Mr. F. William Valentino, President New York State Energy, Research, and Development Authority 2 Rockefeller Plaza Albany, NY 12223-1253 t
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