ML17264B065

Forwards Corrections & Clarifications to 970929 LAR Re RCS Pressure & Temp Limits Rept Administrative Controls Requirements,As Result of NRC Review

ML17264B065
Person / Time
Site:	Ginna
Issue date:	10/08/1997
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17264B066	List: ML17264B065 ML17264B067
References
NUDOCS 9710150244
Download: ML17264B065 (5)

Text

CATEGORY,1 REGVLATO INFORMATION DISTRIBUTION LI, STEM (R IDS)

ACCESS~ILFl NBR: 9710150244 DQC. DATE: 97/20/08 NOTARIZED: YES DOCKET FAt IL 50 244 Rober t Emmet Ginna Nuc lear Planti Unit iI Rochester G 05000244 AUTH. NAME 'UTHOR AFFILIATION MECREDY R. C. Rochester Gas 5 Electric Corp.

RECIP. NAME REC IP IENT AFFILIATION VISSINGI G. S.

SUBJECT:

Foreards corrections to proposed low temp oevrpressure protection TS.

DISTRIBUTION CODE: AQOID COPIES RECEIVED: LTR r ENCL SIZE:

TITLE: OR Submittal: General Di strib uti on License Exp date in accordance T NOTES: uJith 10CFR2I 2. 109(9/19/72). 05000244 E

RECIPIENT COPIES REC IP IENT COP I ES ID CODE/NAME LTTR ENCL CODE/NAME =

LTTR ENCL

'D PD1-1 LA 1 PDi-1 PD 1 0 VISSINGI G. 1 1 INTERNAL: 1 NRR/DE/ECGB/A 1 NRR/DE/EMCB 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 OGC/HDS3 1 0 EXTERNAL: NQAC NRC PDR 1 1 Q i BC N

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AND ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 FASTAVENUE, ROCHESTER, N. Y 14849-0001 ARFA CODE716 546-2700 ROBERT C. MECREDY Vice President Nuclear Operations October 8, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555

Subject:

Corrections to Proposed Low Temperature Overpressure Protection Technical Specifications Rochester Gas &, Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244

Reference:

Letter from R.C. Mecredy, to G.S. Vissing, NRC,

Subject:

Application for Amendment to Facility Operating License, Revision to Reactor Coolant System PCS) Pressure and Temperature Limits Report (PTLR) Administrative Controls Requirements, September 29, 1997.

Dear Mr. Vissing,

l By the above reference, RG&E submitted a license amendment request (LAR) related to the Ginna Station Pressure and Temperature Limits Report (PTLR). During the performance of the NRC review, several errors and questions were identified. Therefore, attached please find the necessary corrections and clarifications to the September 29th LAR. These are provided in Enclosure 1 to this letter and summarized below:

Attachments II and III are revised to correct several typographical errors (i.e., ensure consistency between the two attachments) and to reference this document since minor errors within the low temperature overpressure protection (LTOP) methodology are also corrected by this letter.

Sections 2.2, 2.3.1, and 5.0 of Attachment IV are updated to: (a) reference the calculation which specifies the LTOP enable temperature; (b) correct a typographical error in Reference 3; and (c) reference this letter for reasons as described in 1 above.

Attachments V and VI are revised to delete the last paragraph of Section 3.3 and to modify the last paragraph of Section 3.4 to clarify the technical specification restrictions on reactor coolant pump starts.

These revised pages should be, substituted for those submitted in the referenced LAR 97i0150244 97i008 PDR ADQCK 05000244 P PDR II!Illllllllllllllllllllllllllllillllll

A questiqn was also raised with respect to whether the LTOP enable temperature was actually specified within Attachment VIIof the September 29th LAR and whether this temperature was also a limitation for reactor coolant pump (RCP) starts. RG8'cE had previously submitted a calculation which determined a LTOP enable temperature of a 306.3'F (see April 24, 1997 LAR, Attachment VII). This calculation remains valid since the heatup and cooldown curves from which the enable temperature is derived remain unchanged. A copy of this analysis is also being provided within this submittal. With respect to RCP starts, Ginna Station Technical Specifications LCO 3.4.6, Note 2 and LCO 3.4.7, Note 3 prohibit RCP starts below the LTOP enable temperature unless the secondary-to-primary temperature difference is < 50'F or the pressurizer water volume is < 324 cubic feet (38% level).

Very t y yours, Robert C. Mecredy Subscribed and sworn to before me on this 8th day of October 1997.

Notary Public DEBORAH A.PIPERNI Notary Pubbc rn the State of New YorIt ONTARIO COUNTY MD&949 Cornnussion Expires Nov. 23, 19,S'IL Attachments xc: U.S. Nuclear Regulatory Commission Mr. Guy Vissing (Mail Stop 14B2)

PWR Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector Mr. F. William Valentino, President New York State Energy, Research, and Development Authority 2 Empire State Plaza Albany, NY 12223-1253

Replacement pages for September 29, 1997 LAR

1. Attachment II - page 5.0-22

2. Attachment III- page 5.0-22

3. Attachment IV - pages 3 and 5

4. Attachment V - pages 3-8 and 3-9

5. Attachment VI - pages 3-7 and 3-8

6. RGB'esign Analysis DA-ME-97-031, Revision 0.