ML17264B041

Forwards Application for Amend to License DPR-18,revising Administrative Controls W/Respect to RCS Pressure & Temp Limits Rept

ML17264B041
Person / Time
Site:	Ginna
Issue date:	09/29/1997
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17264B042	List: ML17264B041 ML17264B043 ML17264B044 ML17264B045
References
NUDOCS 9710020172
Download: ML17264B041 (6)

Text

CATEGORY 1 REGULAiY INFORMATION DZSTRIBUTI+YSTEM (RIDE)

ACCESSION NBR:9710020172 DOC.DATE: 97/09/29 NOTARIZED: YES DOCKET I FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME MECREDY,R.C.

RECIP.NAME AUTHOR AFFILIATION Rochester Gas 6 Electric Corp.

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SUBJECT:

.Forwards application for amend to license DPR-18,revising Administrative Controls w/respect to Reactor Coolant Sys Pressure & Temp Limits Rept.

DISTRIBUTION CODE: AOOZD TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution J ENCL $ SIZE: + (Q P A T

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 E

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-1 LA ' 1 PD1-1 PD 1 1 0 VISSINGFG. 1 1 INTERN  : FILE CENTER 0 1 1 NRR/DE/ECGB/A 1 1 R~Pj EM 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 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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NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSZON 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12

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AND ROCHESTER GAS ANDElECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N. Y 1>I6d9.000I AREA CODE716 5'-2700 ROBERT C. MECREDY Vice President Nvcieor Operations September 29, 1997 U.S. Nuclear Regulatory Commission Document Control Desk At.: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555

Subject:

Application for Amendment to Facility Operating License, Revision to Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)

Adminstrative Controls Requirements Rochester Gas & Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Vissing,

The purpose of this letter is to seek an amendment to the Facility Operating License to revise the specified methodology for determining the low temperature overpressure protection (LTOP) enable temperature setpoint, update the existing PTLR for various issues, and revise the Adminstrative Controls section to place future changes to the PTLR under licensee control.

The original license amendment request (LAR) related to this issue was submitted to NRC by Reference (a). As a result of subsequent correspondence between the NRC and RG&E (see References (b) through (d)), numerous changes were requested of the original LAR. Consequently, this submittal supersedes the Reference (a) LAR in its entirety and incorporates all changes requested in References (b) through (d).

Summarily, consistent with Generic Letter 96-03, this letter provides the following:

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a. An LAR(Attachments I, II, and III) which revises Administrative Controls Section 5.6.6 of the Ginna Station Technical Specifications to perform the following:

Replace the reference to the May 23, 1996 NRC letter (which is the basis for the existing LTOP and pressure/temperature (P/T) limits) with a new reference containing gp the NRC's approval of the first use of the LTOP methodology specified within the

~g Administrative Controls section.

Implement necessary changes to place the PTLR under licensee control.

Update the list of documents containing the approved NRC methodology to reference WCAP-14040-NP-A for the P/T curves and this letter which contains the 97i0020i72 970929 PDR ADQCK 05000244 P PDR

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methodology for the LTOP setpoints and enable temperature (Attachment VI).

iv. Correct a typographical error within the Administrative Controls.

b. Revision 2 of the PTLR (Attachment IV) which contains the following:

i. Update of all reactor vessel material information as documented in WCAP-14684 (Attachment VIII).

n. The LTOP enable temperature and pressure setpoint using the methodology submitted as Attachment VI to this letter. Though the methodology would allow for the LTOP enable temperature to be lowered (Attachment VII), RG&E has elected to keep the current conservative higher LTOP enable temperature shown in PTLR Section 2.2.

iii. Update of the Pfl'urves based on the methodology of Reference (e) as documented in WCAP-14684 (Attachment VIII).

Please note that there is no change to WCAP-14684 and the PTLR (other than updates of the methodology references) from that provided in Reference (a). A revised response to previous NRC questions concerning the LTOP methodology is also provided in Attachment IX (Ref. (b), Enclosure 3).

Upon approval of this LAR, the PTLR will become an RG&E controlled document such that future changes will not require NRC approval as long as the methodology specified in the Administrative Controls section is used. Since the existing PTLR expires on December 31, 1997, RG&E requests NRC consideration ofthis LAR by December 12, 1997 in order to support necessary implementation.

Ve y yours, obert C. Mecredy ECG~rCB:

(a) Letter from R.C. Mecredy, RG&E, 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), dated April 24, 1997.

(b) Letter from R.C. Mecredy, RG&E, to G.S. Vissing, NRC,

Subject:

Clarifications to Proposed Lcnv Temperature Overpressure Protection(LTOP) Technical Specification, dated June 3, 1997.

(c) Letter from R.C. Mecredy, RGAE, to G.S. Vissing, NRC,

Subject:

Request for Exemption Pom 10CFR50.60, "Accepfance Criteria for Fracture Prevention for Light Wafer Nuclear Power Reactors for Normal, dated June 12, 1997.

(d) Letter from G.S. Vissing, NRC, to R.C. Mecredy, RG8'cE,

Subject:

Exemption From the Requirements of 10 CFR Part 50.60, Acceptance Criteria for Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation - RL. Ginna Nuclear Power Planf (TAC No. M98993), dated July 2S, 1997.

(e) WCAP-14040-NP-A, Methodology Used to Developed Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves January 1996.

MD&941 Attachments xc: Mr. Guy S. 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 Valentine, President New York State Energy, Research, and Development Authority 2 Empire State Plaza Albany, NY 12223-1253