ML17158B870
| ML17158B870 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/18/1996 |
| From: | Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| NUDOCS 9611260068 | |
| Download: ML17158B870 (5) | |
Text
November 18, 1996 Mr. Robert G. Byram Senior Vice President
- Nuclear Pennsylvania Power 5 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101
SUBJECT:
PLANT PERFORMANCE REVIEW (PPR) - SUSQUEHANNA STEAM ELECTRIC STATION
Dear Mr. Byram:
On November 7, 1996, the NRC staff completed the semiannual Plant Performance Review (PPR) of the Susquehanna Steam Electric Station.
The staff conducts these reviews for all operating nuclear power plants to develop an integrated understanding of safety performance.
The results are used by NRC management to fac.',"..'ate planning and allocation of inspection resources.
The PPR for Susquehanna involved the participation of all technical divisions in evaluating inspection results and safety performance information for the period May 1996 through October 1996.
PPRs provide NRC management with a current summary of licensee performance and serve as inputs to the NRC Systematic Assessment of Licensee Performance (SALP) and senior management meeting (SMM) reviews.
This letter advises you of our planned inspection effort resulting from the Susquehanna PPR review.
It is provided to minimize the resource impact on your staff and to allow for scheduling conflicts and personnel availability to be resolved in advance of inspector arrival onsite.
The enclosure details our inspection plan for the next 6 months.
The rationale or basis for each inspection outside the core inspection program is provided so that you are aware of the reason for emphasis in these program areas.
Resident inspections are not listed due to their ongoing and continuous nature.
We will inform you of any changes to the inspection plan.
If you have any questions, please contact Walter J. Pasciak at 610-337-5258.
OR'.GINAL SIGNED BY:
Walter J. Pasciak, Chief Reactor Projects Branch 4 Division of Reactor Projects Docket Nos. 50-387;50-388
Enclosure:
Inspection Plan 96ii260068 9hiii8 PDR ADOCK 05000387 6
Mr. R. Byram cc w/encl:
G. T. Jones, Vice President
- Nuclear Engineering G. Kuczynski, Plant Manager J. M. Kenny, Supervisor, Nuclear Licensing G. D. Miller, Manager - Nuclear Engineering R. R. Wehry, Nuclear Licensing M. M. Urioste, Nuclear Services Manager, General Electric C. D. Lopes, Manager - Nuclear Security W. Burchill, Manager, Nuclear Safety Assessment H. D. Woodeshick, Special Office of the President J, C. Tilton, III, Allegheny Electric Cooperative, Inc.
Commonwealth of Pennsylvania
Mr. R. Byram Distribution w/encl:
Region I Docket Room (with concurrences)
Nuclear Safety Information Center (NSIC)
K. Gallagher, DRP M. Oprendek, DRP D. Screnci, PAO NRC Resident Inspector PUBLIC Distribution w/encl: (Via E-Mail)
W. Dean, OEDO C. Poslusny, Project Manager, NRR J. Stolz, PDI-2, NRR Inspection Program Branch, NRR (IPAS)
R. Correia, NRR R. Frahm, Jr., NRR DOCUMENT NAME:
To receive a copy of this docu e ii N
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'Copy without attachment/encfosure E
~ Copy with attachment/enclosure OFFICE NAME DATE RI:DRP.
PSw tland 11/
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96 OFF CIAL RECORD COPY
SUSQUEHANNA INSPECTION PLAN IP NUMBER TITLE DATE IP 40500- CO Effectiveness of Licensee Controls in Identifying, Resolving, and Preventing Problems May 97 IP 37550 - CO Engineering
- Visit 4 IP 84750 - CO Radioactive Waste Treatment and Effluent and Environmental Monitoring (Effluents) 3/10/97 1/13/97 IP 92904-RI IP 92720 - RI IP 84750- CO Followup - Radiological Controls Corrective Action (Due to accumulated HP concerns and recent performance history)
Radioactive Waste Treatment and Effluent and Environmental Monitoring (Environs)-
IP 82701 - CO Operational Status of the Emergency Preparedness Program 3/3/97 4/21/97 1/13/97 IP - NRC Inspection Procedure CO - Core Inspection (NRC Program Requirement)
Rl - Regional Initiative Inspection
SUSQUEHANNA INDEPENDENT SPENT FUEL STORAGE INSTALLATION(ISFSI) INSPECTION PLAN IP NUMBER IP 37828-RI TITLE Installation and Testing of Modifications DATE TBD COIVIMENTS Contingent on PPSL's readiness for this inspection.
This is for reactor building crane inspection (heavy loads) for ISFSI.
50.59 evaluation in progress (ECD is 12/31/96).
IP 60851 - RI IP 60852 - RI Design Control of ISFSI Components ISFSI Fabrication by Outside Fabricators TBD This is for Dry Shielded Cask (DSC) fabrication, scheduled for 1/15 - 4/25/97.
DSC delivery is 5/6/97.
DRS Support (Vendor inspection has lead).
- Rl IP 60853 - RI Design Control of ISFSI Components; On-site Fabrication of Components and Construction of an ISFSI TBD 60851 - Should be done reasonably close to dry run, currently scheduled to start on 8/8/97, and after onsite fabrication (McGinty, NMSS, to lead, with support from Anderson); 60853 - DRS (Carrasco) has lead (HSM delivery is about mid-January 1997).
IP 60854 - RI IP 60854-Rl IP 60855 - Rl Preoperational Testing of an ISFSI Preoperational Testing of an ISFSI Operation of an ISFSI TBD TBD TBD This is a Procedures Review, to be conducted by PE (Swetland).
Must be done before Dry Run.
This is the Dry Run Inspection, to be conducted by PE and resident inspectors.
Operation of ISFSI, to be conducted by PE (Swetland) and resident inspectors.
IP - NRC Inspection Procedure CO - Core Inspection (NRC Program Requirement)
Rl - Regional Initiative Inspection