ML17263A762
| ML17263A762 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/23/1994 |
| From: | Andrea Johnson Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-M89473, NUDOCS 9408310318 | |
| Download: ML17263A762 (7) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 23, 1994 Docket No. 50-244 LICENSEE: Rochester Gas ahd Electric Corporation FACILITY: R.
E. Ginna Nuclear Power Plant
SUBJECT:
SUMMARY
OF AUGUST 3,
- 1994, TELECONFERENCE WITH ROCHESTER GAS AND ELECTRIC CORPORATION ON THEIR REVISED OUALITY ASSURANCE PROGRAM FOR STATION OPERATION, REVISION 20 (TAC NO. M89473)
During a teleconference with Rochester Gas and Electric Corporation (RGEE) on August 3, 1994, at 1:30 p.m., the U. S. Nuclear Regulatory Commission (NRC) staff discussed their concerns regarding the revised guality Assurance Program for Station Operation (gAP),
Rev.
20, submitted May 16, 1994.
Revision 20 incorporates quality assurance related changes associated with the reformatting of the administrative controls, Section 6.0 of the Ginna Technical Specifications (TS).
RGKE agreed to modify Revision 20 of the gAP and to modify their License Amendment Request (LAR) submittal to resolve the level of detail needed to relocate the TS sections into the gAP.
Provided below are the details of the issues that were discussed by the staff.
Also a list of attendees is enclosed.
One issue the staff addressed was the relocation of the review and organizational units from the TS to gAP, Rev.
20.
The staff said that the level of detail, specifically in the sections addressing the Plant Operations Review Committee (PORC) and the Nuclear Safety Audit and Review Board (NSARB),
TS 6.5. 1 and TS 6.5.2., that was originally incorporated in the TS was not retained in QAP, Rev.
20.
The staff expressed concern that
- gAP, Rev.
20 does not specify the composition, meeting frequency, responsibilities, authority, records, etc., of the PORC.
The staff also expressed concern that
- gAP, Rev.
20 does not address the qualifications, engineering background, and the number of years experience of members of the NSARB.
In Rev.
20 of the
These sections involve the responsibility for reviewing Ginna station procedures prior to their approval.
The staff addressed this point in the teleconference and said that an equivalent level of detail is necessary in the gAP as in sections 6.8.2 and 6.8.3 of the TS.
In addition, the staff voiced concerns regarding the elimination of several regulatory requirements from the TSs as specified in the LAR submitted by RGLE on May 16, 1994.
The staff said that since TS 6.2.2.b and 6.2.2.c are incorporated in the new Standard Technical Specifications (STS), they could not be eliminated from the TSs.
Additionally, RGKE, in its LAR, Attachment A, justifies removal of TS 6.9.2.
1 by stating that reporting requirements related to sealed sources are specified in 10 CFR 30.50.
The staff,
- however, cautioned RGKE that 10 CFR 30.50 does 00
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P August 23, 1994 not deal with sealed sources reporting; rather, 10 CFR 39.35 deals with sealed source testing and reporting.
The staff further cautioned RG&E that 10 CFR 39.35 is only-applicable to sealed sources used in well logging.
The technical specifications and the reporting requirements, TS 6.9.2. 1, are derived from this regulation.
However, the staff views that removal cannot be based on this regulation.
The staff also found removal of TS 6. 17 is not justified by 10 CFR 50.59.
The staff expressed concern about the relocation of current administrative requirements to other controlled documents as specified in the LAR.
The staff asserted that the justification presented by RG&E for the relocation of TS 6.2. l.b and TS 6.2. I.d is not acceptable.
Therefore, the staff views that these sections cannot be removed from the TS.
The staff also raised the point that TS 6.7.b and TS 6.7.d are being evaluated by a review branch of the NRC to determine if generic titles are acceptable and how they should be specified in the TS.
The staff, furthermore, agreed to the use of generic titles for the offsite review committees specified in the changes made to TS 6.7.c and TS 6.7.d; however they emphasized that the generic titles may have to be referenced to the Updated Final Safety Analysis
- Report, Chapter 13.4.
Furthermore, NRC staff pointed out that TS 6.8. l.i are still incorporated in the STSs, and therefore could not be relocated from the TSs.
During the teleconference, RG&E committed to submitting the modified Revision 20 of the gAP on August 12,
- 1994, and the modified LAR during the week of August 15, 1994.
In view of the modified gAP and LAR submittal, the staff said they require an extension from their originally scheduled commitment date of September 9,
1994.
After receiving the submittal from RG&E and discussing the new commitment date with appropriate staff members, the NRC staff will present a new commitment date.
Original signed by:
Allen R. Johnson, Project Manager Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
1.
List of Attendees cc w/enclosures:
see next page DISTRIBUTION w/encl osure:
Docket File NRC
& Local PDRs PDI-3 Reading R.
Zimmerman W. Russell/F. Hiraglia S.
Varga C. Miller (A)
W. Butler S. Little S. Halik K. Cotton A. Johnson OGC E. Jordan S. Black F. Allenspach C. Grimes B. Giardina R. Cooper, RI H. Kaplan M. Modes ACRS (10)
J. Linville, RI W. Dean, RI
- reviousl concurred
".:,OF~F,:::I'CE.,:
l','.NAME-'::."~
j<.DAT.E""'Ai'l PDI-A SL'ie
'f/B3/94 PDI-3' PDI-3'Ha ik:dt AJohnson K /~94
'5 g/94
- RPEB FAllenspach 08/22/94
- OTSB PDI-3: D BGi ardina WButl e 08/23/94 8 /g9/94 OFFICIAL RECORD COPY DOCUMENT NAME: B:iGIHTGSUH.803
C I
e
August 23, 1994 not deal with sealed sources reporting; rather, 10 CFR 39.35 deals with sealed source testing.and reporting.
The staff further cautioned RG&E that 10 CFR 39.35 is only applicable to sealed sources used in well logging.
The technical specifications and the reporting requirements, TS 6.9.2. 1, are derived from this regulation.
However, the staff views that removal cannot be based on this regulation.
The staff also found removal of TS 6. 17 is not justified by 10 CFR 50.59.
The staff expressed concern about the relocation of current administrative requirements to other controlled documents as specified in the LAR.
The staff asserted that the justification presented by RG&E for the relocation of TS 6.2. l.b and TS 6.2. l.d is not acceptable.
Therefore, the staff views that these sections cannot be removed from the TS.
The staff also raised the point that TS 6.7.b and TS 6.7.d are being evaluated by a review branch of the NRC to determine if generic titles are acceptable and how they should be specified in the TS.
The staff, furthermore, agreed to the use of generic titles for the offsite review committees specified in the changes made to TS 6.7.c and TS 6.7.d; however they emphasized that the generic titles may have to be referenced to the Updated Final Safety Analysis
- Report, Chapter 13.4.
Furthermore, NRC staff pointed out that TS 6.8. l.i are still incorporated in the STSs, and therefore could not be relocated from the TSs.
During the teleconference, RG&E committed to submitting the modified Revision 20 of the gAP on August 12,
- 1994, and the modified LAR during the week of August 15, 1994.
In view of the modified gAP and LAR submittal, the staff said they require an extension from their originally scheduled commitment date of September 9,
1994.
After receiving the submittal from RG&E and discussing the new commitment date with appropriate staff members, the NRC staff will present a new commitment date.
Enclosure:
List of Attendees Allen ohn n, Project Manager Project Directorate I-3 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation cc'/enclosure:
See next page
Dr. Robert C. Hecredy R.E.
Ginna Nuclear Power Plant CC:
Thomas A. Moslak, Senior Resident Inspector R.E.
Ginna Pl.ant U.S. Nuclear Regulatory Commission 1503 Lake Road
- Ontario, New York 14519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Ms.
Donna Ross Division of Policy Analysis
- 5. Planning New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Charlie Donaldson, Esq.
Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Nicholas S.
Reynolds Winston
& Strawn 1400 L St.
N.W.
Washington, DC 20005-3502 Ms. Thelma Wideman
- Director, Wayne County Emergency Management Office Wayne County Emergency Operations Center 7370 Route 31
- Lyons, New York 14489 Hs. Mary Louise Meisenzahl Administrator, Monroe County Office of Emergency Preparedness 111 West Fall Road, Room 11 Rochester, New York 14620 Dr. Robert C. Hecredy Vice President, Nuclear Production Rochester Gas and Electric Corporation 89 East Avenue Rocherster, New York 14649
ENCLOSURE List of Attendees August 3,'1994 GINNA equality Assurance Program for Station Operation, Revision 20
~Name Title Walt Butler Director Allen Johnson Project Manager Fred Allenspach Performance
& equality Evaluation Branch NRR/DRPE/PD I-3 NRR/RPEB 301-504-1497 301-504-1039 Phone Number NRR/DRPE/PD I-3 301-504-1433 Bob Giardina Technical Specifications Branch George Wrobel, Manager Nuclear Safety
& Licensing Hark Flaherty Nuclear Safety
& Licensing Charlie Anderson Manager of equality Assurance Joe Widay Plant Manager Tom Harlow Ginna Production Superintendent Steve Adams Ginna Technical Assistant Karen Cotton Project Engineer NRR/OTSB RG&E RG&E RG&E RG&E RG&E RG&E NRR/DRPE/PD I-3 301-504-3152 716-724-8070 716-724-8512 716-724-8119 315-524-4446 Ext.
250 315-524-4446 Ext. 315 315-524-4446 Ext. 494 301-504-1438 Sarah Halik Engineering Intern NRR/DRPE/PD I-3 301-504-2021
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