ML19210A142
| ML19210A142 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/17/1975 |
| From: | METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19210A141 | List: |
| References | |
| NUDOCS 7910240864 | |
| Download: ML19210A142 (1) | |
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First Year Operation Report Three Mile Island Nuclear Staticn Unit 1 (DiI-1}_
Operating License No. DPR-50 Locket No. 50-269 1.0 Unit Perferrance TM'-1 cc=pleted ene year of ec==ercial cperation on September 2,1975. A summary of opel. ir-experience is centained in the TMI-l Monthly Cperating R.7c.rts cc ering a period of time. Cumulative unit availability and ca.ac't facters af 07.05 and Sk.85 respectively were attained. Further=cre, during the first year of cannercial cperatien 24I-1 systems and cc=ponents performed as predicted except as noted in 2.0 belev.
2.0 Reassessment of the Safety Analysis for Substantial Variances frc=
Specifications Reassess =ents cf the Safety Analysis for substantial variances frc=
specifiaations have been made on a case by case basis with each cf our Nonrcutine 30 Oay Reports (Th-01 thru Th-Oh and 75-01 thru 75-08). None of these variances are interrelated to the extent that one variance vculd have an adverse impact en safety analysis cf the other. Further with the belev noted exceptions these variance: have been corrected and the issues are considered closed.
A.
NRR-30 75-06 Dredging operations vill begin as soon as the apprcpriate permits, all-ready applied for, are obtained.
B.
NRR-30 75-08 Scre insulation ecnditiens that are contributing to increased Reactor Building heat lead have been identified and it is anticipated that these vill be corrected during the upcc=ing refueling outage.
3.0 Assessment of the Performance of Structures, Systems and Cc=penents Imrortant to Safety.
The Reacter Building Structural Integrity Test (SIT) Repcrt, the Precperational Integrated Leak Test Repcrt, and the Ring Girder Surveillance Test Repcrts Six Menths and Cne Year after SIT, provide assessments cf the performance of the Reactor Building.
All other structures, systems and cc=ponents impcrtant to safety have perfer=ed within design predictions except as noted in Abncr=al and Nonrcutine repcrts and high lighted belev.
A.
Hydraulic Shock Suppressors (Snubbers) 1490 038 Abncrmal Occurrence Reperts 7h-20, Th-23, Tk-25, TL-30, 75-03, 75-CS,
75-09 and 75-3h all dealt with incperative snubbers. Mest of these cccurrences resulted frc= failure cf the snubber seal material.
Subsequently a seal replacement and snubber inspecticn program was initiated at IMI-1.
Later, as a result cf other industry experience, the NEC requested Technical Specificatien to require snubber inspecticn.
This request was respcnded to by cur Technical Specification change request No. 19 aubmitted en August 23, 1975 7910240 f
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3.
Reactor Pressure Instrument Trip Setroints Drift of the reactor pressure instrument setpcints has been reported in Abncr=al Occurrence Repcrts Th-24, 75-15, 75-16, 75-19 and 75-26.
Cne of the icng term corrective actions asscciated with these reports was to request a change to the Technical Specifications to allev drift of the setpoints within the limits assumed in the safety analysis.
This proposed change vill be reviewed fer conformance to the recently issued (for ec==ent) regulatory guide 1.105 (ncv. 1975) prior to submission to the 3EC.
C.
Vent Header Syste=
As a result several Enviren= ental Incident reports involving unplanned radicactive releases frc= the Vent Header System, the NRC requested that this system be reevaluated and changes be made as necessary to prevent future unplanned releases. In the interim it was requested that changes to the Technical Specificatiens and operating procedures be made to ninimize the possibility of additional releases. The operating procedures have been revised and a request to change the Technical Specifications was submitted en June 13, 1975 Design changes to the Vent Header syste=are the final approval stages and hardware changes are expected to be cc=plete in May 1976.
k.0 Progress and Status Report on Ite=s Recuirinz Additional Information The ite=c requiring additional information have either been addressed and the issues are closed or they are listed belev:
A.
Anticipated Transients Without Sera = (ATWS)
It is car understanding that for the category of plants in which TMI-1 falls this issue is closed until NRC review of previously submitted information is cc=plete.
3.
Kidney Filter The installation of a kidney filter system vill be accceplished during the up-cc=ing refueling cutage.
C.
ECCS This issue has been addressed in our submittals of July 9, July 15, August 8 and Cctober 23, 1975 and is avaiting NRC review.
D.
Pressurizer Level The opti=um pressurizer level prcgram to =inimize level variaticns during transients was identified during the Startup Test Fregram as an area that could be further impreved. Although the experienced level variatiens during lead transients are acceptable it is felt that the response could be further optimized. At this point it is felt that a means to optimize performance has been determined and should be 2:plemented by May 1976.
1490 039
F s
E.
Main Steam Safety Valves During the Startup Test Fregram it was felt that the relief settings of these valveu cculd be adjusted to impreve plant resperse to transients. Opti=um settings for these valves have been determined and the valves have been appropriately adjusted.
F.
Accidental Orop of a Spent Fuel Cask This issue was identified as requiring additional information en August 23, 197h, when Met-Ed was requested to prcvide additicnal information in this area. Subsequently our letter cf Feb. 21, 1975 provided most of the requested infer =aticn, the remainder vill be submitted by Jan. 31, 1976.
G.
Reacter Vessel Support System A response to the URC request for information (Cet. 15, 1975) is being prepared at this time.
E.
TMI Dikes and Rip Rap This issue has been addressed and a status report was submitted en Sept. 29, 1975 I.
Sodium Thiosulfate and Sedium Hydrcxide Tank Dravdcvn Times This issue has been addressed in cur letter of Oct. 13, 1975 1490 040