ML17263B065

Forwards Application for Amend to License DPR-18,revising TSs in Entirety by Converting to Improved TSs

ML17263B065
Person / Time
Site:	Ginna
Issue date:	05/26/1995
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML17263B066	List: ML17263B065 ML17263B067
References
NUDOCS 9506080198
Download: ML17263B065 (10)

Text

g' O'RIDRITY ACCELERATED Rl DS P l<OCESSli G) 1 I

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

~ CCESSION NBR:9506080198 DOC.DATE:-95/05/26 NOTARIZED: YES DOCKET

'FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR. AFFILIATION Rochester Gas & Electric Corp.

MECREDY,R.C.

RECIP.NAME JOHNSON I A.R.

RECIPIENT AFFILIATION Pro'ect Directorate I-1 ( PD1-1 ) ( Post 941001 )

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SUBJECT:

Forwards application for amend to license DPR-18,revising TSs in entirety by converting to improved TSs.

~: fo+>7oD TITLE: OR Submittal: General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 LA 1 1 PD1-1 PD 1 1 JOHNSON,A 1 1 INTERNA IBE CENT 0 1 1 NRR/DE/EMCB 1 1 B 1 1 NRR/DS SA/S PLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

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YOTE TO ALL "RIDS" RECIPIEYTS:

PLEASE HELP US TO REDUCE lVKSTE! COYTAC'f'I'I IE DOCL'IIEET CONTROL DESK, ROOKI Pl-37 (EXT. 504-~083 ) TO ELI XIIX.ATEYOI.'R %ANIL FROW!

f DIS Rl 8UTIOY LIS'I'S I'OR DOCI. 5,1I.'X'I'S 0'Ol.'ON'"I'L'I'.D!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 11

AND ROCHESTER GAS AND EIECTRIC CORPORATION ~ 89 FASTAtrrENUE, ROCHESTER, N. Y Id&f9-0001 ARFA CODE716 56-2700 ROBERT C. MECREDY Vice President Nucteor Operations Hay 26, 1995 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-1 Washington, D.C. 20555

Subject:

Application for Amendment to Facility Operating License Conversion to Improved Technical Specifications Rochester Gas & Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Hr. Johnson,

The enclosed License Amendment Request (LAR) proposes to revise the Ginna Station Technical Specifications in its entirety by converting to Improved Technical Specifications (ITS). This LAR also proposes to revise the Ginna Station Operating License. The proposed application is consistent with the original purpose of the Technical Specification Improvement Program as outlined in Reference (a). The technical specification changes withdrawn by Reference (b) are also addressed in this LAR. In addition, the changes requested by Reference (c) are included within this submittal (i.e., this LAR does not supersede Reference (c) but is consistent with the changes being requested).

The proposed ITS contained in this LAR are based on the current Ginna Station Technical Specifications (through Amendment No. 59), NUREG-1431 (Ref. (d)), and other documents. The proposed ITS Limiting Conditions for Operations (LCO) or Surveillance Requirements (SRs) which are less restrictive than the current Ginna Station Technical Specifications (TS) and which are not consistent with NUREG-1431 are listed below (LCOs and SRs are those listed in Attachment C to this letter):

a ~ All refueling interval surveillances were changed from 18 months to 24 months consistent with the guidance of Generic Letter 91-04 (Ref. (e)).

b. Allow both post-accident charcoal filters to be removed from service at the same time provided that both containment spray trains are OPERABLE (LCO 3.6.6 and current Ginna Station TS 3.3.2.2).

c ~ Only require one component cooling water heat exchanger to be OPERABLE when the system is required to be OPERABLE (LCO 3.7.7 and current Ginna Station TS 3.3.3. 1).

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Allow both motor driven auxiliary feedwater (AFW) pumps to be removed from service for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (LCO 3.7.5 and current Ginna Station TS 3.4.2.1.b).

Increase the allowed outage times for certain reactor trip system and engineered safety feature actuation system functions up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (LCO 3.3. 1, LCO 3.3.2, and current Ginna Station TS 3.5. 1 and 3.5.2).

Allow an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to restore an inoperable reactor trip breaker or Automatic Trip Logic train in HODES 3, 4, and 5 after exiting HODE 2 with this condition (LCO 3.3. 1 and current Ginna Station TS 3.5. 1).

Allow the use of a closed system to isolate a containment penetration with a failed containment isolation valve (LCO 3.6.3 and current Ginna Station TS 3.6.3).

Only require one offsite power source to be OPERABLE during HODE changes (LCO 3.8. 1 and current Ginna Station TS 3.7.2. l.b.2, 3.7.2.2.a, and 3.7.2.2.b).

Allow 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to reduce the Power Range Neutron Flux trip Function setpoint when Fo or F~ is not within limits (LCO 3.2. 1, LCO 3.2.2, and current Ginna Station TS 3. 10.2.2).

Remove the requirement to test certain reactor coolant system pressure isolation valves when the plant has been in cold shutdown for > 7 days (SR 3.4. 14. 1 and current Ginna Station TS 4.3.3. 1).

Remove the requirement to test the motor driven AFW pump cross-over motor operated isolation valves (LCO 3.7.5 and current Ginna Station TS 4.8.3).

Remove the requirement to verify that the AFW pumps and valves can actuate within 10 minutes (LCO 3.7.5 and current Ginna Station TS 4.8. 10).

Increase the allowed tolerances for the pressurizer safety valves setpoint (LCO 3.4. 10 and current Ginna Station TS 3.3. 1.3.a).

Increase the allowed fuel enrichment limit from 4.25 weight percent to 5.05 weight percent (Specification 4.3. l. I.a and current Ginna Station TS 5.3.1.b).

Relocate the following parameters and setpoints to the Core Operating Limits Report:

Overpower ~T and Overtemperature ~T parameters (LCO 3.3. 1 and current Ginna Station TS 2.3.1.2.d and 2.3.1.2.e).

Refueling water storage tank (RWST) boron concentration (LCO 3.5.4 and current Ginna Station TS 3.3. l. l.a and 3.3. 1.2).

Accumulator boron concentration (LCO 3.5. 1 and current Ginna Station TS 3.3.1.l.b and 3.3.1.3).

iv. SHUTDOWN MARGIN (LCO 3. 1. 1 and current Ginna Station TS 3. 10. 1. 1 and Figure 3.10-2).

p. Relocate the containment integrity requirements during refueling (i.e.,

NODE 6) from the technical specifications (current Ginna Station TS 3.5.2, 3.5.5, and 3.8. l.a).

q. Relocate the Reactor Coolant Pump Underfrequency trip Function from technical specifications (current Ginna Station TS 2.3. 1.2.g and 3.5. 1).

r. Relocate the AFW and Standby AFW system manual initiation functions from technical specifications (current Ginna Station TS 3.5.2).

The above changes, while different from NUREG-1431 and the current Ginna Station TS, are consistent with the Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors (Ref. (f)) and the accident analyses.

The changes are discussed in detail i'n Attachment A.

Revision 0 of NUREG-1431 was used for the preparation of this LAR since Revision 1 has only recently been issued. However, all approved Travellers which were used to generate Revision 1 are addressed in this submittal. The only exception is Traveller BWR-26, C. 1 related to LCO 3.0.4. This Traveller has not been generically evaluated for the Westinghouse plants as required by the Reviewer's Note added as part of this approved Traveller. Therefore, RG&E has elected to defer implementation of this Traveller until after this evaluation has been performed.

We request that NRC approval of this LAR be provided by November 20, 1995. This approval date is required to support an implementation date in February 1996 since included within this LAR is a change in the allowed fuel enrichment limit.

This enrichment limit is being changed to support conversion to 18 month refueling cycles with the new fuel scheduled to be shipped by Westinghouse beginning in February 1996. The technical evaluation of this change in enrichment was previously submitted to the NRC by Reference (g).

With an implementation date in February 1996, all surveillances as proposed in Attachment C will be current with the following exceptions:

a~ SR 3.6.6. 13 - This requires a verification every 5 years of the spray additive flow rate through each eductor path. The current Ginna Station TS do not contain this requirement. However, recirculation flow from the RWST through the eductors is performed monthly. In addition, sample lines associated with the spray additive tank have not previously demonstrated blockage. A review'of industry events related to the spray additive tank also did not reveal any concerns with respect to blockage.

b. SR 3.7.3.1 - This requires a verification every 24 months that each main feedwater pump discharge valve (HFPDV) can close within 80 seconds following receipt of an actual or simulated signal. The current Ginna Station TS do not contain this requirement. However, the HFPDVs were last tested on April 14, 1992 with one valve closing in 73. 1 seconds and the second valve closing in 75.9 seconds. These values are within the 80 second limit and provide assurance of the HFPDVs OPERABILITY.

Based on the above information, RG&E requests that these SRs be deferred until the refueling outage scheduled to begin by April 1, 1996.

RG&E would like to note that we have requested an exemption to 10 CFR 50, Appendix K, Sections I.D.3 and I.D.5 with respect to upper plenum injection issues (Ref. (h)) which, when approved, would result in a change to the Ginna Station license. This change is not addressed, or otherwise included within this LAR.

The final implementation date will be coordinated with the NRC following final approval of this LAR. Any questions related to this LAR should be directed to Hark Flaherty at (716) 724-8512.

Very truly yours, Robert C. Hecre y MDFX612 Attachments

References:

(a) Letter from R.C. Hecredy, RG&E, to A.R. Johnson, NRC,

Subject:

Conversion to Improved Technical Specifications, dated February 28, 1994.

(b) Letter from R.C. Hecredy, RG&E, to A.R. Johnson, NRC,

Subject:

License Amendment Application Requests, dated April 26, 1995.

(c) Letter from R.C. Mecredy, RG&E, to A.R. Johnson, NRC,

Subject:

Application for Amendment to Operating License Reactor Coolant Activity Technical Specifications, dated Hay 23, 1994.

(d) NUREG-1431, Standard Technical Specifications, westinghouse Plants, Revision 0, September 1993.

(e) Generic Letter 91-04, Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Nonth Fuel Cycle, dated April 2, 1991.

(f) NRC, Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 21, 1993.

(g) Letter from R.C. Mecredy, RG&E, to A.R. Johnson, NRC,

Subject:

Technical Specification Improvement Program, dated Hay 5, 1995.

(h) Letter from R.C. Mecredy, RG&E, to A.R. Johnson, NRC,

Subject:

Request for Exemption to Selected 10 CFR Part 50, Appendix K Requirements, dated November 5, 1992.

xc: U.S. Nuclear Regulatory Commission Mr. Allen R. Johnson (Mail Stop 14B2)

PWR Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission (2 copies)

Mr. Carl Schulten Office of Technical Specifications Branch (Mail Stop 011E22)

Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Hr. Gerry L. Jones INEL Lockeed Idaho Hail Stop 3870 2525 Freemont Avenue Idaho Falls, ID 83415-3870 Hr. Clyde Morton PQP 301 Hartz Avenue Suite 206 Danville, CA 94526-3328 Ms. Donna Ross New York State Energy Office Ginna Senior Resident Inspector Hr. Jim Andrachek Westinghouse Electric Company Energy Center East 4-1 4350 Northern Pike Honroeville, PA 15146-2886 Hr. Donald Hoffman EXCEL Services Corporation 11921 Rockville Pike Suite 100 Rockville, HD 20852 Hr. Gene Eckholt (copy of Attachment C, F, and G only)

Northern States Power Company Prairie Island Nuclear Generating Plant Route 2 Welch, HN 55089 Mr. Thomas Malanowski (copy of Attachments C, F, and G only)

Wisconsin Electric Power 231 West Michigan Milwaukee, WI 53201

Nr. Rick Pulec (copy of Attachments C, F, and G only)

Wisconsin Public Service P.O. Box 19002 700 North Adams Green Bay, WI 54307-9002

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Hatter of )

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Rochester Gas and Electric Corporation ) Docket No. 50-244 (R.E. Ginna Nuclear Power Plant)

APPLICATION FOR AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the U.S. Nuclear Regulatory Commission (NRC), Rochester Gas and Electric Corporation (RG&E), holder of Facility Operating License No. DPR-18, hereby requests that the license and the Technical Specifications set forth in Appendix A to that license be amended.

This request for change is to convert the entire Technical Specifications to Improved Technical Specifications format. Several requirements are also relocated to other programs and documents in accordance with the criteria contained in the NRC Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors.

A description of the amendment request, necessary background information, justification of the requested change, and no significant hazards and environmental considerations are provided in Attachment A. This evaluation demonstrates that the proposed changes do not involve a significant change in the types or a significant increase in the amounts of effluents or any change in the authorized power level of the facility. The proposed changes also do not involve a significant hazards consideration.

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