JPN-94-013, Application for Amend to License DPR-59,revising TS, Proposing New SRV Performance Limits to Take Credit for Currently Installed SRV Capacity

From kanterella
(Redirected from JPN-94-013)
Jump to navigation Jump to search
Application for Amend to License DPR-59,revising TS, Proposing New SRV Performance Limits to Take Credit for Currently Installed SRV Capacity
ML20064C880
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 03/02/1994
From: Josiger W
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20064C882 List:
References
JPN-94-013, JPN-94-13, NUDOCS 9403100301
Download: ML20064C880 (7)
v • d • e


Text

't 123 Main street Whde Plains, New York 10601 914 081 4200

  1. b NewYorkPower (sv Authority March 2,1994 JPN-94-013 U. S. 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 Proposed Change to the Technical Specifications Regarding Updated SRV Performance Requirements and Miscellaneous Chanaes (JEISdl.10171

REFERENCES:

See attached list

Dear Sir:

The Authority is revising a docketed FitzPatrick Technical Specification amendment application (Reference 1) to reflect the NRC staff's recent approval (Reference 2) of a BWROG (Boiling Water Reactor Owners' Group) Licensing Topical Report (Reference 3). Attachments I and 11 are Technical Specification pages and the Safety Evaluation, respectively, revised to reflect the staff's decision. These attachments supersede and replace those submitted with our original application.

The Authority submitted an application for an amendment to the FitzPatrick Technical Specifications proposing new Safety / Relief Valve (SRV) performance limits to take credit for the currently installed SRV capacity. Since the Authority submitted its request, the BWROG submitted a similar request as Licensing Topical Report NEDC-31753P.

The NRC staff recently concluded that NEDC-31753P provides an acceptable basis for all but two of the changes requested by the Authority. Specifically, the NRC staff concluded that the use of an upper limit was not an acceptable means to reduce the number of LERs (Licensee Event Reports) and that SRVs with setpoints outside of a 3 percent tolerance must be considered inoperable. Attachments I and 11 reflect the staff's j

decision on these two issues.

OS' M7 h'

9403100301 940302 PDR ADOCK 05000333 P

PDR

'i These changes were discussed in a September 3,1993 telephone conversation between Mr. Brian McCabe of your staff and Messrs. Bob Penny and Judd Ellmers of the Authority, if you have any questions, please contact Mr. J. A. Gray, Jr.

Very traly yours, 7

f,d/f '"

M y

/W. A. Josi er

(. Acting Ex cuti e Vice President Nuclear G,eneration

~~_d

3 I

cc:

Regional Administrator -

U. S. Nuclear Regulatory. Commission 475 Allendale Road King of Prussia, PA.19406 Office of the Resident inspec' tor U. S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 Mr. Brian C. McCabe Project Directorate 1-1 Division of Reactor Projects-l/II U. S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, DC 20555 i

Ms. Donna Ross New York State Energy Office 2 Empire Stato Plaza 16'" Floor Albany, NY 12223 1

1 4

4 e

em w

r-

~

,e r

e

=r

.J I

References:

1. NYPA letter, J. C. Brons to NRC (JPN-80-084) dated December 20,1989, regarding " Proposed Change to the Technical Specifications Regarding Updated SRV Performance Requirements and Miscellaneous Changes (JPTS-89-017)."
2. NRC letter, A. C. Thadani to C. L. Tully, dated March 8,1993, l

regarding " Acceptance for Referencing of Licensing Topical Report NEDC-31753P,'BWROG In-Service Pressure Relief Technical Specification Revision Licensing Topical Report (TAC No. M792650)'."

3. BWROG letter, G. J. Beck to R. C. Jones, Jr. (BWROG-9036) dated July 9,1990. Transmits technical report "BWROG In-Service Pressure Relief, Technical Specifications Revision, Licensing Topical Report, NEDC-31753P" dated February 1990.

4.

NYPA letter, J. C. Brons to NRC (JPN-90-010) dated January 16,1990 regarding " Proprietary Material Supporting the Change to the Technical Specifications regarding Updated SRV Performance "

5. NYPA letter, R. E. Beedle to NRC (JPN-92 001) dated January 1,1992 regarding " Response to Request for Additional information Regarding Proposed Change to the Technical Specifications Regarding Updated SRV Performance Requirements and Miscellaneous Changes (JPTS-89-017)."
6. NYPA letter, R. E. Beedle to NRC (JPN-92-005) dated January 30,1992, regarding " Proprietary Material Supportirig the Proposed Change to the Technical Specifications Regarding Updated SRV Performance Requirements and Miscellaneous Changes (JPTS-89-017)."

i

7. NYPA letter, R. E. Beedle to NRC (JPN-93-033) dated May 5,1993, regarding " Proposed Change to the Technical Specifications Regarding Updated SRV Performance Requirements and Miscellaneous Changes (JPTS-89 017)."
8. NYPA letter, R. E. Beedle to NRC (JPN-93-038) dated May 26,1993, regarding " Proposed Change to the Technical Specifications Regarding Updated SRV Performance Requirernents and Miscellaneous Changes (JPTS-89-017)."
9. NRC letter, D. E. LaBarge to J. C. Brons dated May 8,1990 regarding,

" Proposed Technical Specification Change Regarding Updated SRV Performance Requirements - James A. FitzPatrick Nuclear Power Plant (TAC NO. 755561) l

..=

i.

Attachments: 1.

Replacement Pages for New York Power Authority Proposed Change to the FitzPatrick Technical Specifications Regarding Updated SRV Performance and Miscellaneous Changes (JPTS-89 017).

11. Revised Safety Evaluation For Proposed Technical Specification Changes Regarding Updated SRV Performance Requirements.

(JPTS-89-017),

t l

Attachment I to JPN-94-013 l

Replacement Pages for New York Power Authority Proposed Change to the FitzPatrick Technical Specifications Reaardina Undated SRV Performance and Miscellaneous Chances (JPTS-89-017)

New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59

Attachment I to JPN-94-013 Instructions:

These pages supersede and replace those submitted with the Authority's original application; NYPA letter JPN-89-084, dated December 20,1989. Three of the pages, indicated by asterisks in the following table, have been revised to reflect the NRC staff's position on the acceptability of NEDC-31753P. The remaining pages, not affected by the NRC staff's position are included to provide a complete " supersede and replace" package.

All pages have been updated as appropriate to reflect amendments issued since the Authority's initial application was filed. Specific changes to each of the pages are summarized in the following table.

1 No.

Remove Replace Note Page Page 1*

27 27 Revised Specification 2.2.1.B to remove mention of " upper limit."

2*

29 29 Revised Bases 1.2 and 2.2 to remove mention of

" upper limit" and to reflect intervening Amendment 190.

3 80 80 Revised Table 4.2-2 to reflect intervening Amendments 169,181, and 201.

4 119 119 Reprinted with more accurate revision bars.

5 120 120 Added revised Specification 4.5.D.2 inadvertently omitted from original application. Also revised to reflect intervening Amendments 148 and 179.

6 128 128 No changes from original application.

7 142a 142a Revised Specification 4.6.E to reflect intervening Amendments 134 and 195.

8 143 143 Revised Specifications 3.6.E.5 and 4.6.E.2 to reflect intervening Amendments 179 and 195.

9*

152 152 Revised Bases 3.6 and 4.6 to remove merulon of

" upper limit."

t

-

Retrieved from "https://kanterella.com/w/index.php?title=JPN-94-013,_Application_for_Amend_to_License_DPR-59,revising_TS,_Proposing_New_SRV_Performance_Limits_to_Take_Credit_for_Currently_Installed_SRV_Capacity&oldid=4444844"