ML17139A726
| ML17139A726 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/09/1982 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| NUDOCS 8206140387 | |
| Download: ML17139A726 (10) | |
Text
'0 Docket No.:
50-387 JUN 9 DISTRIBUTION:
document Control (50-38~7)
"--NRC-PDR-L PDR NSIC PRC 11r..
Norman 'll. Curtis Vice President - Engineering 5
Construction - Nuclear Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101
Dear Hr. Curtis:
LB82 Reading EHylton RLPerch
Region I
Subject:
Status of Outstanding Items'o Support Operating Licensing for Susquehanna, Unit 1 The following list of outstanding items contains both open and confirmatory issues for which an applicant response is still required.
Each of these items must be completed prior to issuance of a low-power license to support fuel loading.
This list does not contain outstanding items on bulletins and circula'rs, construction deficiency reports, TMI items, violations or unresolved inspection issues to be addressed to NRC, Region I.
Item 1.
Environmental qualification program - 100K completion required prior to licensing.
2.
Undervoltage issue on startup busses during LOCA conditions.
3.
Documentation of results for the reactor, RPV intervals, NSSS piping and supports for the LOCA plus SSE loads including the effects of annulus pressurization.
4.
Four-page summary forms for all the NSSS supplier equipment.
5.
Technical bases 'for no equipment damage as result of fatigue cycling effects due to safety relief valve loadings.
6.
Provide conformance to NUREG-0803 or acceptable equivalent for gA and as-built inspections.
'7.
Verification of inleakage assumption and 60-second drawdown time to re-establish a -0.25 inches of water guage pressure from secondary containment leak test.
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Perform test which would determine the limitations and capabilities of BltR to maintain safe reactor and containment conditions in event of loss of all AC power, and provide detailed test procedures and safety analysis for NRC review.
9.
Provi'de design documentation, for Post-accident sampling capability.
10.
Interim containment purge valve qualifications and completion of logic modifications for containment isolation signals.
To allow for adequate NRC staff review on your submittals without impacting your July 15, 1982 fuel load date, responses to each of these items must be received by June 18, 1982. If submittals cannot be provided by June 18, 1982, additional discussions should be held with the NRC staff with regard to the scheduled fuel load date.
Sincerely, cc:
See next page Robert L. Tedesco, Assistant Director for Licensing Division of Licensing
- SEE PREVIOUS'CONCURRENCES ON NEXT PAGE.
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Docket No.:
50-387 Mr. Norman W. Curtis Vice President - Engfneyrfng 8
Construction - Nucleag Pennsylvania Power 8 Ligh Company 2 North Ninth Street Allentown, Pennsylvania 18 1
Dear Mr. Curtis:
DISTRI 8 UTION:
Document Control (50-387)
NRC PDR L
PDR NSIC PRC LB82 Reading EHylton RLPerch
- Cutchin, OELD I&E ACRS (16)
Region I
Subject:
Status of Outstanding tern to Support Operating Licensing for Susquehanna, Unit 1
The following list of outstanding ite s contains both open and confirmatory issues for which an applicant re ponse fs still required.
Each of these items must be completed prior t fssuan e of a low-power license to support fuel loading.
This list does n t contain, outstanding items on bulletins and cfrculars, construction de fcfency reports, TMI items, vfolatfons or unresolved inspection issues t be address d to NRC, Region I.
Item l.
Environmental qualfffca fon program - 100% completion required by June 30, 1982.
2.
Undervoltage issue on tartup busses during L CA conditions.
3.
Documentation of resu ts for the reactor, RPV
- ntervals, NSSS piping and supports for the LOCA plus SSE loads includ ng the effects of annulus pressurfzatf n.
4.
Four-page summary f rms for all the NSSS supplfer equipment.
5.
Technical bases fo no equipment damage as result f fatigue cycling effects due to sa ety relief valve loadfngs.
6.
Provide conforma ce to NUREG-0803 or acceptable equivalent for gA and as-built inspec ons.
OFFICEI SURNAME/
DATEQ NRC FORM 318 (1040) NRCM 0240
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7.
Verification of inleakage assumption and 60-second drawdown time to re-establish a -'0.25 inches of water guage pressure from secondary contain-ment leak test.
8.
Perform test which would determine the limitations and capabilities of BWR to maintain safe reactor and containment conditions.in event of loss of all AC power, and provide detailed test procedures and safety analysis for NRC review.
9.
Provide design documentation for Post-accident sampling capability.
10.
Interim containment parve valve qualifications and completion of logic modifications for containment isolation signals.
To allow for adequate NRC staff review on your submittals without impacting your July 15, 1982 fuel load date, responses to each of these items must be received by June 18, 1982. If submittals cannot be provided by June 18, 1982, additional discussions should be held with the NRC staff with regard to the scheduled fuel load date, Sincerely, cc:
See next page Robert L. Tedesco, Assistant Director for Licensing Division of Licensing OFFICE II SURNAME/
DL:LB82/
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','Susquehanna Mr. Norman M. Curtis Vice President Engi neering and Construction Pennsyl vania Power
& Light Company Allentown, Pennsyl vania 18101 ccs:
Jay Silberg, Esquire Shaw, Pittman, Potts
& Trowbridge 1800 N Street, H. M.
Mashington, D.
C.. 20036 Edward M. Nagel, Esquire General Counsel and Secretary Pennsyl vania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Milliam E. Barberich Nuclear Licensing Group Supervisor Pennsylvania Power
& Light, Company 2 North Ninth Street Allentown, Pennsyl vania 18101 Mr. G. Rhodes Resident Inspector P. 0.
Box 52 Shickshinny, Pennsylvania 18655 Gerald R. Schultz, Esquire Susquehanna Environmental Advocates P. 0. Box 1560 Milkes-Barre, Pennsylvania 18703 Mr. E. B. Poser Project Engineer Bechtel Power Corporation P. 0.
Box 3965 San. Francisco, California 94119
~
Dr. Judith H. Johnsrud Co-Director
'nvironmental Coalition on Nuclear Power 433 Orlando Avenue State College, Pennsylvania 16801 Nr. Thomas M. Gerusky, Director Bureau of Radiation Protection Resources Commonwealth of Pennsyl vania P. 0.
Box 2063
'arri
- sburg, Pennsyl vania 17120 Ns. Colleen Marsh.
. P. 0.
Box 538A>>
RD PT4 Mountain Top, Pennsyl vania 18707 Nr. Thomas J. Halligan Correspondent The Citizens Against Nuclear Dangers P. 0. Box 5
- Scranton, Pennsyl vania 18501 Mr. J.
W. Nillard Project Manager Nail Code 395 General Electric Company 175 Curtner Avenue San J ose, California 95125 Robert M. Adler, Esquire'ffice of Attorney General 505 Executive House P. 0.
Box 2357 Harri sburg, Pennsyl vania 17120
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