ML20151H860
| ML20151H860 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Oyster Creek |
| Issue date: | 09/26/1983 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | John Miller Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20151H203 | List:
|
| References | |
| FOIA-86-26 NUDOCS 8310040077 | |
| Download: ML20151H860 (8) | |
Text
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8 S:ptemb:r 26, 1983 Docket No. 50-219 MEMORANDUM FOR:
James R. Miller, Chief Operating Reactors Branch #3, DL FROM:
Dennis M. Crutchfield, Chief Operating Reactors Branch #5, DL
SUBJECT:
REQUEST FOR PUBLICATION IN MONTHLY FR NOTICE - NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO PROVISIONAL OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND OPPORTUNITY FOR A HEARING GPU Nuclear Corporation, Docket No. 50-219, Oyster Creek Nuclear Generating Station, Ocean County, New Jersey Date of amendment request: May 21, 1982 Description of amendment request: Request for amendment to the license to allow operation of the reactor with the existing core spray sparger subject t: :nhanced inspectiun and ieputLing requirements.
Basis for proposed no significant hazards consideration determination:
License Amendment No. 47, dated May 1!i, 1980, to License No. DPR-16 for the Oyster Creek Nuclear Generating Station added a license condition which requires the replacement of the existing cracked core spray sparger during the current cycle 10 refueling outage. Operation with a cracked sparger f'or an interim fuel cycle prior to the current refueling outage was pennitted based on repairs to the sparger using repair bracket assemblies. The NRC Staff concluded in the Safety Evaluation supporting Amendment No. 47 that this interim repair of the Oyster Creek sparger does not constitute a significant change in safety margin from that of the original design and that installation of the repair hardware would not increase the probability of an accident.
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e James R. Miller, Chief September 26, 1983
' During the current refueling outage, the licensee has completed full-inspection ~of the accessible surfaces and welds of the sparger and repair assemblies'using new inspection techniques and computer photo enhancedent and has compared indications of cracks to previous indications. The new inspections and analyses appear to show that:
(1) many previous indications of cracks from prior inspections are, in fact, not cracks; (2) no further degradation of the sparger has occurred since the prior inspections; and (3) susceptibility to new cracking (stress corrosion cracking postulated to result from high residual stresses from forcing pipes into position during r
installation and sensitization from welding, cold work etc.) in new locations is reduced by stress relief from existing cracks.
Moreover, analysis of the seismic, static and thermal loadings for the repair bracket assemblies (which were analyzed, designed and installed in accordance with currently accepted engineering practices) demonstrate the repair bracket assemblies' ability to limit crack openings to an. acceptable range should existing cracks propogate around the sparger circumference and inspection data obtained during the current refueling outage indicates tha't the repair bracket assemblies are capable of maintaining the integrity of the system. The staff has concluded that continued operation of the facility can be permitted if the extent of sparger cracking remains as evaluated in the SER supporting Amendment 47.
To ensure that no degradation in performance of the sparger will occur, the licensee will perform full inspections of the accessible surfaces and welds of both core spray spargers and repair assemblies at each refueling outage. Comparisons of the results wit'h previous inspection will be made along with an evaluation of the safety significance of any new or progressing indications.
This information will
-- a -
O James R. Miller, Chief September 26, 1983 be provided to.the NRC staff for review. Based on staff review of the inspection-results and safety evaluations, the staff will determine if the sparger needs to be replaced during the outage or whether the facility can be allowed to restart. This decision will b'e founded on the detemination of whether or not safety margins have been significantly reduced from levels currently in the sparger.,
Because, subject to NRC Staff confimation prior to issuance of the proposed amendment, the magnitude of sparger cracking is not as severe as (
previously indicated, there has been no additional degradation during the i last fuel cycle, and the repair bracket assemblies should maintain the integrity of the existing sparger as it has been maintained during the last
' fuel cycle, the NRC Staff proposes to determine that issuance of the pro-posed amendment authorizing operation with the existing repaired sparger without further degradation until the end of life does not involve a signi "
ficant increase in the probability or consequences of accidents previously considered, does not create the possibility of a new or different accident from any evaluated previously, and does not involve a significant reducti'o'n in a margin of safety, all relative to previously approved operation.
Accordingly, the NRC Staff proposes to determine that this license amendment would not involve significant hazards consideration.
Local Public Document Room location:
101 Washington Street, Toms River, New Jersey 08753.
Attorney for licensee:
G.F. Trowbridge, Esquire, Shaw, Pittman, Potts and Trowbridge,' 1800 M Street, N.W., Washington, D.C.
20036.
James R. Miller September 26, 1983 NRC Branch Chief:
Dennis M. Crutchfield
~~
Original signed,by Dennis M. Crutchfield, Chief Operating Reactors Branch f5 Division of Licensing cc:
Docket ORB #5 Reading J. Lombardo H. Smith
- SEE PREVI0'US TISSUE FOR CONCURRENCE DL: ORB #5*
DL: ORB #5*
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/A HSmith:cc J ombardo DCr chfield C"^dh 2d F
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James R. Miller, Chief "
be provided to-the NRC staff for review.
Based on staff review of the inspt::t'orrTesults and safety evaluations, the staff will determine if the sparger ne'eds to be replaced during the outage or whether the facilitf can be allowed to restart. This decision will be founded on the determination of whether or not safety margins have been significantly reduced from levels currently in the sparger..
Because, subject to NRC Staff confirmation prior to issuance of the proposed amendment, the magnitude of sparger cracking is not as severe as previously indicated, the repair bracket assemblies should maintain the integrity of the existing sparger as it has been maintained during the last fuel cycle, the NRC Staff proposes to determine that issuance of the pro-C posed amendment authorizing operation with the existing repaired sparger without further degradation until the end of life does not involve a signi-ficant increase in the probability or conse'quenc'es of accidents previously considered, does not create the possibility of a new or different accident from any evaluated previously, and does not involve a significant reduction in a margin of safety, all relative to previously approved operation.
Accordingly, the NRC Staff proposes to determine that this license amendment I
does not involve significant hazards considerations.
local Public Document Room location:
101 Washington Street, Toms River, New Jersey 08753.
Attorney for licensee:
G.F. Trowbridge q uire, Shaw, Pittman, Potts and Trowbridge,1800 M Street, N.W., Washington, D.C.
20036.
NRC Branch Chief:
Den s M. Crutchfield DLfJ
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Original signed by HSnit :cc JLpmb L
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't /g Dennis M. Crutchfield, Chief Operating Reactors Branch #5 DL: ORB #5 OEL DL: AD/SA ~ Division of Licensing DCrutchfield CL.5 FMiraglia l
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Robert A. C1crk, Chief during the current outage and review of the inspection data indic,ates that they are capable of maintaining the integrity of the system, and they will not increase the possibility of a new or different kind of an ace'ident.
Thus, if analysis of the inspection datik shows that the magnitude of the problen is not as sehere as was prehiously indicated, and that no degra-
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dation has occurred since the licensee's initial inspection, there wi.11 be no significant hazard inholhed with' continued operation of the as-repaired facility for the next fuel cycle.
Based on the abohe discussion, the staff proposes to detemine that the action doesenot inholhe a sibnificant increase in the probability or consequences of an accident previously evaluated, does not create the possibility of a new or different kind of accident from any prehiously evaluated and does not involhe a signific it reduction in a marg n of safety. /.ccordingly, the staff propose to.detemine that the requested action involhes no significant hazards consideration.
Local Pubite Document Room location:
101 tlashington Street, Txs Riher, New Jersey 03753.
Attorney for licensee:
G.F. Trowbridge, Esquire, Shaw, Pittaan, Potts and Trowbridge, 1800 M Street, N.tl.,liashington, D. C.
20036.
l Dennis M. Crutchfield
'RC Branch Chief:
Dennis H. Crutchfield, Chief Operating Reactors Branch f5 Division of Licensing cc:
Docket' ORB #5 P,eading J. Ltynbardo
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w Robert A. Clark, Chief,
.Thus, if it is shown that the magnitude of the problem is not as severe as w3s previous'1y indicated, there is reasonable assurance'that the health.and safety of the general public will not b'e jeopardized by.
continued operation of the as-repaired facility for the next fuel cycle.
Based on the above discussion, the staff proposes to determine that the action does not involve a significant increase in the probability or consequences of an accident previously evaluated, does not create the possibility of a new or different kind of accident from any previously evaluated or does not involve a significant reduction in a margin of safety. Accordingly, the staff proposes to determine that the requested action involves no sibn,jficant hazards consideration.
Local Public Document Room location:
101 Washington Street. Toms' River,
!!cw Jersey 03753 Attorney for licensee:
G.F. Trowbridge, Esquire, Shaw, Pittman, Potts and Trowbridge,1000 li Street, ll.W., Washington, D.C.
20036 I!RC Branch Chief:
Dennis 11. Crutchfield Dennis M.' Crutchfield, Chief Operating Reactors Branch !5 Division of Licensing cc: Docket OP.B f5.Redding..
J. Lombardo H. Salth
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Robert A. Clark Local Public Document Room location:
101 Washington Street.
Toms Fiverr-New Jersey 08753 Attorney for licensee:
G. F. Trowbridge, Esquire, Shaw, Pittman.
Potts and Trowbridge, 1800 M Street, N. W., Washington, D. C.
20036 NRC Branch Chief:
Dennis M. Crutchfield Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing cc:
Docket File (w/INSHC)
ORB Reading H. Smith J. Lombardo 3
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c:ASHINGT N. D. C. 20555 C, w ff September 26, 1983 Docket No. 50-219 MEMORANDUM FOR:
James R. Miller, Chief Operating Reactors Branch #3, DL FROM:
Dennis M. Crutchfield, Chief Operating Reactors Branch #5, DL
.. ~
SUBJECT:
REQUEST FOR PUBLICATION IN MONTHLY FR NOTICE - NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO PROVISIONAL OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND OPPORTUNITY FOR A HEARING GPU Nuclear Corporation, Docket No. 50-219, Oyster Creek Nuclear Generating Station, Ocean County, New Jersey Date of amendment request: May 21, 1982 Description of amendment request:
Request for amendment to the license to allow operation of the reactor with the existing core spray sparger subject to enhanced inspection and reporting requirements.
Basis for proposed no significant hazards consideration determination:
License Amendment No. 47, dated May 15, 1980, to License No. DPR-16 for the Oyster Creek Nuclear Generating Station added a ligense condition which requires the replacement of the existing cracked core spray sparger during the current cycle 10 refueling outage.
Operation with a cracked sparger for an interim fuel cycle prior to the current refueling outage was permitted based on repairs to the sparger using repair bracket assemblies. The NRC Staff concluded in the Safety Evaluation supporting Amendment No. 47 that this interim repair of the Oyster Creek sparger does not constitute a significant change in safety margin from that of the original design and that installation of the repair hardware would not increase the probability of an accident, h
y 3 / oo'Lo oT/
7
James R. Miller, Chief September 26, 1983
- During the current refueling gutage, the licensee has completed full inspection ~of the accessible surfaces and welds of the sparger and repair assemblies using new inspection te:Sniques and computer photo enhancentent and has compared indications of cracks to previous indications. The new inspections and analyses appear to show that:
(1)manypreviousindications of cracks from prior inspections are, in fact, not cracks; (2) no further degradation of the sparger has occurred-since the prior inspections; and (3) susceptibility to new cracking (stress corrosion cracking postulated to result from high residual stresses from forcing pipes into position during installation and sensitization from welding, cold work etc.) in new locations is reduced by stress relief from existing cracks.
Moreover, analysis of the seismic, static and thermal loadings for the repair bracket assemblies (which were analyzed, designed and installed in accordance with currently accepted engineering practices) demonstrate the repair bracket assemblies' ability to limit crack openings to an acceptable range should existing cracks propogate around the sparger circumference and inspection data obtained during the current refueling outage indicates tha't the repair bracket assemblies are capable of maintaining the integrity of the system.
The staff has concluded that continued operation of the facility can be permitted if the extent of sparger cracking remains as evaluated in the SER supporting Amendment 47.
To ensure that no degradation in performance of the sparger will occu', the licensee will perform full r
inspections of the accessible surfaces and welds of both core spray spargers and repair assemblies at each refueling outage.
Comparisons of the results with previous inspection will be made along with an evaluation of the safety significance of any new or progressing indications.
This information will 4
[
James R. Miller, Chief September 26, 1983 be provided to.the NRC staff for review.
Based on staff review of the inspection.-results and safety evaluations, the staff will determine if the sparger needs to be replaced during the outage or whether the facility can be allowed to restart. This decision will be founded on the determination of whether or not safety margins have been significantly reduced from levels
.. ~
j currently in the sparger.,
l Because, subject to NRC Staff confirmation prior to issuance of the
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1 l
proposed amendment, the magnitude of sparger cracking is not as severe as j
previously indicated, there has been no additional degradation during the 1
i last fuel cycle, and the repair bracket assemblies should maintain the 1
]
integrity of the existing sparger as it has been maintained during the last l
fuel cycle, the NRC Staff proposes to determine that issuance of the pro-1 l
posed amendment authorizing operation with the existing repaired sparger j
with:ut further degradation until the end of life does not involve a signi-ficant increase in the probability or consequences of accidents previously
)
considered, does not create the possibility of a new or different accident i
from any evaluated previously, and does not involve a ignificant reductio'n j
in a margin of safety, all relative to previously approved operation.
i Accordingly, the NRC Staff proposes to determine that this license amendment would not involve significant hazards consideration.
]
Local Public Document Room location:
101 Washington Street, Toms River, New Jersey 08753..
Attorney for licensee:
G.F. Trowbridge, Esquire, Shaw, Pittman, Potts and Trowbridge, 1800 M Street, N.W., Washington, D.C.
20036.
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I James R. Miller September 26, 1983 i
I l
NRC' Branch Chief:
Dennis M. Crutcl} field
?xgRL:J DennisM.Crutchfield/ Chief t
Operating Reactors Bfanch #5 l
Division of Licensing cc: Docket l
ORB #5 Reading l
J. Lombardo H. Smith G
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