ML17264A863
| ML17264A863 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/24/1997 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17264A865 | List: |
| References | |
| GL-96-03, GL-96-3, NUDOCS 9705020083 | |
| Download: ML17264A863 (5) | |
Text
CATEGORY REGULAT INFORMATION DISTRI'BUTION STEM (RIDS)
ACCESSION NBR:9705020083 DOC.DATE: 97/04/24 NOTARIZED: YES DOCKET
'FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIA'ZION 44 ~~a Pn 7ecA VISSING,G.S.
'gP~Cp
SUBJECT:
Forwards application for amend to license DPR-18
& TS.Rev to RCS PT limits rept re administrative controls requirements.
DISTRIBUTION CODE:
R012D COPIES RECEIVED:LTR J ENCL j SIZE:
TITLE: License Amendment Requests NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 T
E RECIPIENT COPIES E
LTTR ENCL INTERNA 'ILE CENTER 01 1
1 RECIPIENT ID CODE/NAME NRR/DRPM/PDLR COPIES LTTR ENCL 1
1 0
EXTERNAL: NRC/PDR 1
1 D
E N,
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 EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 3
ENCL 3
e
v ANn ROCHESTER GASANDELECTRIC CORPORATION ~ 89 EASTA trENIJE, ROCHESTER, N. Y ldi$d9-0001 ARFA CODE716 5'-27M ROBERT C. MECREDY Vice President Nvciearoperotions April24, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy S. Vissing Project Directorate I-l Washington, D.C.
20555
Subject:
Application for Amendment to Facility Operating License, Revision to Reactor Coolant System (RCS)
Pressure and Temperature Limits Report (PTLR)
Administrative Controls Requirements Rochester Gas & Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Vissing,
By Reference (a), RG&E submitted a license amendment request (LAR) with respect to Administrative Controls Section 5.6.6 of the Ginna Station Technical Specifications.
This LAR was intended to update the Ginna Station PTLR and revise the necessary Administrative Control requirements such that the PTLR would come under licensee control (i.e., future changes to the PTLR would be permitted in accordance with the methodology specified in the Administrative Controls section)
~
Following NRC review of that LAR, questions arose with respect to the low temperature overpressure protection (LTOP) system enable temperature specified in the PTLR. Specifically, the NRC identified that the determination ofthe LTOP enable temperature required consideration of RCS liquid temperature measurement accuracy per the methodology currently specified in Specification 5.6.6.
RG&E agreed to address this concern by first submitting a relief request (Ref.
(b))
and then by requesting an exemption to applicable regulations (Ref.
(c)).
Subsequently, the NRC notified RG&E that RCS liquid temperature accuracy should instead be addressed by a LAR which updated the methodology in Specification 5.6.6.
Consequently, the purpose of this LAR is to replace the LAR submitted as Reference (a) in its entirety in order to both place the PTLR under licensee control and to provide a new LTOP enable temperature methodology.
As a result, the exemption request provided in Reference (c) is hereby withdrawn since this LAR provides the necessary changes.
~ AA'34 l'705020083 970424 PDR ADOCK 05000244 P
PDR lllllllllllilllllllll,llll,Ill lllllll In summary, consistent with Generic Letter 96-03, this letter provides the following:
a.
An LAR (Attachments I, II, and III)which revises Administrative Controls Section 5,6.6 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 the NRC's approval of the first use of the LTOP methodology specified within the 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 methodology for the LTOP setpoints and enable temperature (Attachment VI).
lv.
Correct a typographical error within the Administrative Controls.
b.
Revision 2 of the PTLR (Attachment IV) which contains the following:
Update ofall reactor vessel material information as documented in WCAP-14684 (Attachment VIII).
The LTOP enable temperature using. the methodology submitted as Attachment VI to this letter.
Though the methodology would allow for the required LTOP enable temperature to be lowered (Attachment VII), RG&E has elected to keep the currently higher LTOP enable temperature shown in PTLR Section 2.2. The remaining LTOP setpoint and methodology remains unchanged as based on the calculation included as Attachment IV to Reference (d).
iii.
Update of the P/T curves 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).
Upon approval of this LAR, the PTLR will become a 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 July 1, 1997, RG&E requests NRC consideration of this LAR by June 15, 1997 in order to support necessary implementation.
Ve ruly yours, Robert C. Mecred
~Rferen cd (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 (RCS)
Pressure and Temperature Limits Report (PTLR), dated September 13, 1996.
(c)
Letter from R.C. Mecredy, RG&E, to G.S. Vissing, NRC,
Subject:
Request to Use ASME Code Case N-514 in the Determination of Low Temperature Overpressure Protection (LTOP) Enable Temperature, dated December 18, 1996.
I Letter from R.C.
- Mecredy, RG&E, to G.S.
Vissing, NRC,
Subject:
Request for Exemption to 10 CFR 50.'60 to Use, American Society ofMechanical Engineers (ASME)
Code Case N-514 in the Deterinination ofLow Temperature Overpressure Protection (LTOP) Enable Temperature, dated February 10, 1997.
(d)
Letter from R. C. Mecredy, RG&E, to A. R. Johnson, NRC,
Subject:
Applicationfor Amendment to Facility Operating License Methodology for Low Temperature Overpressure (LTOP) Limits, dated February 9, 1996.
(e)
WCAP-14040-NP-A, Methodology Used to Developed Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves January 1996.
Attachm'ents
" 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 Iong of Prussia, PA 19406 Ginna Senior Resident Inspector Mr. F. William Valentino, President Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399