ML20128E714
| ML20128E714 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/22/1985 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| References | |
| LSO5-85-05-023, LSO5-85-5-23, NUDOCS 8505290453 | |
| Download: ML20128E714 (6) | |
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May 22, 1985 Docket No. 50-219 LS05-85-05-023 Mr. P. B. Fiedler Vice President and Director Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731 Cear Pr. Fiedler:
SUBJECT:
SUPPLEMENT TO INSERVICE INSPECTION (ISI) REVIEW
.Re:
Oyster Creek Nuclear Generating Station By letter dated June 28, 1983, a safety evaluation.(SE) addressing the staff's review of GPU Nuclear's (the licensee's) requests for relief from the inservice inspection requirements of Section XI of the Amer 4can Society o' Mechanical Engineers Boiler and Pressure Vessel Code (the Code) was-forwarded to you. Attached to this SE was the NRC contractor's Technical Evaluation Report (TER) on the Oyster Creek Inservice Inspection Program.
Page 14 of the TER which addressed the licensee's requested relief from the volunetric examination on control rod drive housings (Item Bl.18) was inadvertently left out of the TER.
Because of this, Item 81.18, Control Rod Drive Housing, was left out'of Table 1 of the SE and was not addressed in the SE.
The licensee stated that the basis for requesting relief was that the configurations of the drive housings are not conducive to volumetric examinations according to the required schedule. The conclusion on page 14 of-the TER was that relief from the requirements of Section XI of the 1974 Code should not be granted and that the licensee should request an update to the 1977 Code.
The staff, however, ' concludes that the licensee's basis stated above for requesting relief was valid and that the licensee need not request in update to the 1977 Code because in accorc'arce with 50.55alg)(a)(iv) a licensee may, but is not required to, update to subrecuent editions of the Code crior to the end of the 10-year inspection interval.
The 1977 Code'which the licensee could upgrade to allows visual inspection in place of volumetric inspection in this instance and such visual inspections'are deemed sufficient to detect defects.
Thus, the alternate visual inspections allowed by(this relief should be sufficient.
Therefore, pursuant to 10 CFR 50.55a(g) 6)(1),
we hereby grant the requested relief. The staff has determined that the stated Code requirements are impractical, the granting of this relief is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest considering the burden that would result if the requirements were imposed on your facility.
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F Mr. P.~ B. Fiedler May 22, 1985 We have enclosed the affected page of Table 1 of the SE and the missing page of the TER.
Sincerely, Disinal signed by:
John A. Zwolinski, Chief Operating Reactors Branch #5 Division of Licensing
Enclosures:
As stated cc w/ enclosures:
See next page DISTRIBUTION Docket File NRC POR Local PDR NSIC-
-ORB # 5 Reading
'JZwolinski CJamerson JDonohew ELJordan BGrimes JPartlow OELD ACRS (10)
HThompson ORAB TBarnhart(4)
OPA, CMiles SECY RDiggs
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DL:0RB#5 DE:MTEB DE:AD/MCET OEL JCJamerson:tm JDonohew BDLiaw WJohnston CWoo a' e b'N/
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Mr'. P. B. Fiedler
-. We have enclosed the affected page of Table 1 of the SE and t missing Lpage of_the TER.
Sincerely -
John A. Zwoli ki, Chief Operating R ctors; Branch #5 Division Licensing
Enclosures:
As stated cc w/ enclosures:
See next page DISTRIBUTION Docket-File
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L Mr. P.-B. Fiedler Oyster Creek Nuclear Generating Station Oyster Creek Nuclear Generating Station cc G. F. Trowbridge, Esquire Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 1800 M Street, N.W.
Post Office Rox 445 Washington, D.C.
0036 Forked River, New Jersey 08731 J.B. Liberman, Esquire Commissioner Bishop, Liberman, Cook, et al.
New Jersey Department of Energy 1155 Avenue of the Americas 101 Commerce Street New York, New York 10036
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Newark, New Jersey 07102 Eugene Fisher, Assistant Director Regional Administrator Division of Environmental Quality Nuclear Regulatory Commission Department of Environmental Region I Office Protection 631 Park Avenue 380 Scotch Road King of Prussia, Pennsylvania 19406 Trenton, New Jersey 08628 FWR Licensing Manager GPlf Nuclear 100 Interpace Parkway Parsippany, New Jersey 07054 Deputy Attorney General State of New Jersey Department of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625 Mayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 U.S. Environmental Protection Agency Penien II Of# ice ATTN:
Recioral Padiation Representative 26'Federai Plaza New York, New York 10007
- 0. G. Holland Licensing Manager Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731
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a TABLE 1 (CONTINUED)
CLASS 1 COMPONENTS 1
LICENSEE PROPOSED RELIEF IWB-2600 IWB-2500 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE REQUEST ITEM NO.
EXAM. CAT.
COMPONENT EXAMINED METHOD EXAM.
STATUS Bl.13 B-I-1 Closure Cladding
- 1. Visual. Assess Gen-GRANTED Head and Sur eral Condi-face or tion of 2.Volu-Cladding metric Bl.14 B-I-1 Reactor Cladding Visual Assess Gen-GRANTED Vessel eral Condi-tion of Cladding Under B-N-1 Category Bl."18 B-0 Control Welds Volu.
Surface GRANTED Rod metric Drive Housings El.6 B-F Reactor Nozzle-to-Volu-Volumetric GRANTED Vessel Safe End.
metric From One
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=and Sur-Side Only NSA 4 Face and 100%
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N5B Surface N3A N3B B4.5 B-J Piping Inaccessible Volu-Visual of WITHDRAWN Pipe Welds metric Areas of In Penetra-Penetra-tions:
tions X-5A X-6 During X-5B X-70 Hydrostatic X-3A X-72 Tests X-3B X-7' X-2A X-8 X-2B X-9 X-4A X-10 X-4B X-61 X-12B B4.5 B-J Piping Inacessible Volu-Visual WITHDRAWN Welds Not In metric During Penetration Hydrostatic Test 84.9 B-K-1 Inte-Support Volu-Visual REQUEST grally Welds metric WITHDRAWN Welded 7/82 Supports
5.
Control Rod Drive Housings, Category B-0, Item Bl.18 Code Requirement The volumetric examinations performed during each inspection interval shall include 100% of the welds in 10%
.of the peripheral control rod drive housings.
The examina-tions may be performed et or near the end of the inspection interval.
Code Relief Request Relief is requested from the volumetric examination requirement of Category B-0 for control rod drive housings.
Proposed Alternative Examination Surface examinations w'ill be perfonned in place of volumetric examinations according to the required schedule.
s L'icensee's Basis for Recuesting Relief Component configuration is not conducive to vokumetric examination as recognized by later editions of the Code.
Evaluation These examinations may be deferred to the end of the interval, and the licensee is considering updating to the 1977 Edition, Summer 1978 Addenda, following the next re '
fueling outage. The newer code would allow the proposed surface examination of these welds.
Thus, updating to the newer code, which the licensee may do with NRC approvai per 10 CFR 50.55a(g)(4)(iv), would eliminate the need for Code relief.
Conclusions and Recommendations Since relief is not needed until the end of the inspection interval, relief from Category B-0 requirements should not be granted at this time.
Instead of requesting relief, the licensee should request to update to the 1977 Code, Summer 1978 Addenda, for performing B-0 requirements.
References References 4 and 13.
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