ML20042A199
| ML20042A199 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 03/15/1982 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| TAC-10816, NUDOCS 8203230196 | |
| Download: ML20042A199 (8) | |
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DElsenhut AE0D Docket File f4Padovan IE flRC PDR RIngram ACRS-10
'L PDR DChaney Gray File ORB #4 Rdg Docket 110. 50-3 GELD H0rnstein EBlackwood O
Mr. J. J. !!attimoe 6
Spk Assistant General Manager and 2
Chief Engineer p% % g ((/g,A%
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3 Sacramento Municipal Utility District 6201 S Street
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cy^4 P. O. Box 15830 e
6 Sacranento, California 95813 4 kg D
Dear !!r. Mattimoe:
SUBJECT:
IriSERVICE IllSPECTI0ft (ISI)
The flRC staff has initiated a substantial effort to bring current its approvals of inservice inspection relief requests.
The purpose of this letter is 1) to ensure that the infomation we are supplying to our contractors for review is current and reflects the latest require-nents for your facility, and 2) to obtain additional infomation on your ISI program.
For the Rancho Seco plant, our review will include your subnittals listed in Enclosure 1.
Any earlier submittals on the subject of the ISI Program will be considered obsolete.
Based on your submittals, the proposed inspection interval for this unit is October 1979 to February 1983. liowever, a Hovember 1,1979 revision to 10 CFR 50.55a permits the inspection interval to be 120 months from the date of first connercial operation, lie will therefore be evaluating your submittals based upon the. inspection interval of Octc.ber 1979 to June 1986. Our review will be conducted against the requirements of the 1974 edition of Section XI of the ASilE Code up to and including the S-75 Addenda..
Please detemine if there are any additional previous subnittals that we should be reviewing. Likewise, if there are any additional requests for relief that should be considered for the proposed inspection interval, please verbally infom your NRC Project Manager as soon as possible and submit these requests to us within thirty days of receipt of this letter.
flote that such requests should deal with only the inservice inspection of pressure-bearing components, including supports, and with systen pressure tests. The inservice testing of pumps and valves is being treated separately and you will receive infornation regarding it by separate
'i correspondence.
l omco sun ucu r b 8203230196 820315 PDR ADDCK 05000312
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G PDR OFFICIAL RECORD COPY usam mi-m.m,
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.,W Hr. J. J. Mattimoe Your mquests should include both exenpted components under the terms of the code as well as relief from the requirements of the code in accordance with paragraph g of 10 CFR 50.55a. Also please advise when you are using later cese versions than the S-75 Addenda (per Item (g)(4)(iv) of 10 CFR 50.55a) for certain examinations, particularly how you are meeting "all related requimments" fmm the same version.
Because your previous submittals generally seen to follow the appropriate guidelines, we have proceeded with our review, and have identified a need for additional infomation. Please provide us with the.information mquested in Enclosure 2 in your thirty day subnittal.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore 0lE clearance is not required under P. L.96-511.
Sincerely, sentalsAL SIMD BK, 281. M&*
John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing Enclosums:
- 1. List of Submittals
- 2. Request for Additional Information t
cc w/ enclosures:
See next page I
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I NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY usopo: insi-333.eso
Sacramento Municipal Utility Rancho Seco, Docket No. 50-312 District cc w/ enclosure (s):
' David S. Kaplan, Secretary and Christopher Ellison, Esq.
General Counsel Dian Grueuich, Esq.
Sacramento Municipal Utility California Energy Commission District lill Howe Avenue 6201 S Street Sacramento, California 95825 P. 0. Box 15830 Sacramento, California 95813 Ms. Eleanor Schwartz California S+'te Office Sacramento County 600 Pennsylvania Avenue, S.E., Rm. 201 Board of Supervisors Washington, D. C.
20003 827 7th Street, Room 424 Sacramento, California 95814 Docketing and Service Section Office of the Secretary Business and Municipal Department
'J.S. Nuclear Regulatory Commission Sacramento City-County Library Wohington, D. C.
20555 828 I Street Resident Inspector / Rancho Seco Sacramento, California 95814 c/o U. S. N. R. C.
14410 Twin Cities Road Herald, CA 95638 Dr. Richard F. Cole Atomic Safety S Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Regional Radiation f.epresentative EPA Reaion IX Mr. Frederick J. Shon 215 Fremont Street Atomic Safety and Licensing Board San Francisco, California 94111 Panel U.S. Nuclear Regulatory Commission Mr. Robert B. Borsum Washington, D. C.
20555 Babcock & Wilcox Nuclear Power Generation Division Elizabeth S. Bowers, Esq.
Suite 220, 7910 Woodmont Avenue Chairman, Atomic Safety and Bethesda, Maryland 20814 Licensing Board Panel U.S. Nuclear Regulatory Comission Thomas Baxter, Esq.
Washington, D. C.
20555 Shaw, Pittman, Potts & Trowbridge 1800 M Street, N.W.
l Washington, D. C.
20036 l
l Herbert H. Brown, Esq.
l Lawrence Coe Lanpher, Esq.
Hill, Christopher and Phillips, P.C.
1900 M Street, N.W.
Atomic Safety and Licensing Board Washington, D. C.
20035 Panel U.S. Nuclear Regulatory Commission l
Helen Hubbard Washington, D. C.
20555 P. O. Box 63 Sunol, California 94586 l
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Sacramento Municipal Utility.
District Atomic Safety and Licensing Appeal Mr. Robert H. Engelken, Regional Administrator U. S. Nuclear Regulatory Commission, Region V Board Panel 1990 N. California Boulevard, Suite 202 U.S. Nuclear Regulatory Commission Walnut Creek, California 94596 Washington, D. C.
20555 Alan S. Rosenthal, Chairman Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Connission Washington, D. C.
20555 Dr. John H. Buck Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Christine H. Kohl Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 California Department of Health ATTN: Chief, Environmental Radiation Control Unit Radiological Health Section 714 P Street, Room 498 Sacramento, California 95814 N..
Task A REVIEW DOCUMENT RECORD Unit (s)
Rancho Seco Date Type Subject Matter 4-22-76 Guid.
Generic initial guidance to licensees
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5-19-76 subm.
Response to 4-22-76
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11-17-76 Guid.
Further generic guidance
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1-24-78 SMUD/
NRC ltr Extension request on 5-19-76 commitment
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2-15-78 Reid (NRC)/ Mattimoe (SMUD) ltr Response to 1-24-78; no extension as such
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2-27-78 Mattimoe / Reid subm.
Add outage time to ISI interval; request 10-18-79 end date
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2-2/ proposal 5-30-78 Reid / Mattimoe amend.
Issues amended #20 granting 2-27-78 request, subject to /
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3-16-79 Walbridge (SMUD) / Reid subm.
Proposed Amendment #63 - ISI Tech Spec Changes
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Itr only 7-18-79 Mattimoe / Reid subm.
ISI/IST submittal with RR for 10-18-79 to 2-18-83
<1-13
- 10-2-79 Meeting (informal notes) mtg
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Interim relief based on 7-18-/9 submittal; requests doc.
10-17-79 Reid / Mattimoe notice of changes from 10/3-10/4 medting
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Answers to 9-21-79 questions (not formally transmitted) 12-10-79 Mattimoe_/ Reid subm.
meeting minutes
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12-12-79 Mattimoe / Reid subm.
Revision 1 to Amendment 63 (proposed)
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j REQUEST FOR ADDITIONAL INFORMATION INSERVICE INSPECTION PROGRAM Rancho Seco 1
1.
Reactor Vessel, CRDM Mechanism Bolts and Control Rod Housing Flange Rings (Items Bl.11.1 and 81.11.2; Category B-G-2) t Code relief is explained in NDE-3 (Ref. 1) which states:
" CODE REQUIREMENT: Visual examination of 100% of Control Rod Drive Mechanism (CRDM) bolting during the interval.
BASIS FOR RELIEF REQUEST: Bolting is only accessible for examination when the CRDM is removed. Category B-0 requires that 10% of the peripheral CRDM's (i.e., 3) be removed for examination.
ALTERNATE EXAMINATION: All bolting from removed CRDM's will be visually examined."
This is taken to mean that only bolting on 10% of the peripheral CRDM's plus any CRDM's which need removal for maintenance reasons will be examined.
The following additional information is requested:
1.
Why are the flange rings included in a Category B-G-2 relief request?
2.
Please provide evidence that all bolting on in-place CRDM's is in-accessible. Are any or all bolts on peripheral CRDM's accessible?
What about bolts on CRDM's adjacent to those that have been mmoved for examination or maintenance?
i 2.
Pump Pressure Boundary, Pump Casing Weld (Item B5.6.1; Category B-L-1)
Code relief is explained in NDE-7 (Ref.1) which states the following:
" CODE REQUIREMENT: Category B-L-1 of Table IWB-2600 requires that a volu-metric examination be performed on pump casing welds.
BASIS FOR RELIEF REQUEST: N9 trchniques are currently available for volu-metric examination of thick stainless steel castings.
ALTERNATE EXAMINATION: None until practical techniques are developed."
What state-of-the-art techniques are you studying and developing to comply with the above requirement?
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Program Interval Under the change in Regulation 10 CFR 50.55a effective November 1,1979, the ISI program when finally approved, will cover the last C0 months of the current 10-year inspection interval, i.e., from October 1979 to June 1986.
Does this result in any changes you wish to make in the relief requests?
Do you require other ISI relief?
REFERENCES:
1.
Submittal, J. J. Mattimoe to Robert W. Reid, " Inservice Testing and Inservice Inspection Program", July 18, 1979.
2.
Letter, J. J. Mattimoe to Robert W. Reid, " Formal Documentation of Dis-cussion with Staff on October 3-4, 1979 Regarding Modification to ISI/IST Program", December 10, 1979.
3.
J. J. Mattimoe to Robert W. Reid, Docket No. 50-313, " Proposed Anendment No. 63, Revision 1, Rancho Seco Nuclear Generating Station, Unit No.1",
December 12, 1979.
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