ML17158B762
| ML17158B762 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/19/1996 |
| From: | Cooper R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| NUDOCS 9608280222 | |
| Download: ML17158B762 (5) | |
Text
August 19, 1996 Mr. Robert G. Byram Senior Vice President - Nuclear Pennsylvania Power 5 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101
SUBJECT:
SUSQUEHANNA PLANT PERFORMANCE REVIEW RESULTS
Dear Mr. Byram:
On August 13, 1996, Region I performed a Plant Performance Review (PPR) for the Susquehanna Steam Electric Station, Units 1 and 2, covering the period of February 4, 1996, to July 28, 1996.
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 facilitate planning and allocation of inspection resources.
The PPR for Susquehanna, Units 1 and 2, involved the participation of all NRC Region I technical divisions in evaluating inspection results and safety performance information for the period noted above.
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 reviews.
During this PPR period, there were indications that performance in some areas may be degrading.
For example, there were weaknesses in performance by non-licensed nuclear plant operators relating to conduct of surveillances.
Further, routine independent performance reviews and observations by your self-assessment groups (i.e. Quality Assurance, Independent Safety Evaluation Services) failed to identify these weaknesses.
Also, our inspections identified several long-standing plant issues involving engineering/design support that were not resolved in a timely manner.
We acknowledge the rising level of issues and condition reports identified by your staff in the radiological controls area.
As a result, we have scheduled a management meeting in the NRC Region I office on August 29, 1996, to discuss the details of these issues, including the reasons for the apparent increase in event occurrence.
While your existing corrective action systems are designed to properly identify, evaluate and resolve these issues, we are currently planning to schedule a followup inspection in the Spring of 1997 to review the effectiveness of your actions.
The enclosure to this letter advises you of our planned inspection effort resulting from this latest PPR meeting.
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 eight months.
The rationale or basis for each inspection outside the core inspection p'rogram 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.
9608280222 960819 PDR ADOCK 05000387 6
Mr. Robert G. Byram We will inform you of any changes to the inspection plan.
If you have any questions concerning this letter, please contact Dr. Walter Pasciak at 610-337-5258.
Sincerely, ORIGINAL SIGNED BY:
Richard W. Cooper, II, Director Division of Reactor Projects Docket Nos.
50-387 50-388
Enclosure:
Susquehanna Inspection Plan 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.
Nuclear Safety Information Center (NSIC)
Commonwealth of Pennsylvania
Mr. Robert G. Byram Region I Docket Room (with concurrences)
H. Miller, RA W. Kane, DRA J. Wiggins, DRS DRS Branch Chiefs (6)
W. Pasciak, DRP S. Pindale, DRP
~ NRC Resident Inspector
'Nuclear Safety Information Center (NSIC)
D. Screnci, PAO PUBLIC N. Oprendek, DRP Il K. Gallagher, DRP
~IN
- *'"1 W. Dean, OEDO J, Stolz, NRR C. Poslusny, NRR Inspection Program Branch (IPAS)
DOCUMENT NAME: G:>BRANCH4iPPRLTR2.SUS I
p'o receive a copy of this document, indicate in the botu C
a C y without attachmen sure E ~ Copy with attachment/enclosure "N" ~ No copy OFFICE NAME DATE RI/DRP SPindale 8/
/96 Rl/DRP WPasci 8/
/96 RI/D RI/
SShan W
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SUSQUEHANNA INSPECTION PLAN IP - NRC Inspection Procedure CO - Core Inspection (NRC Program Requirement)
TI - Temporary Instruction (NRR Program Requirement)
IP NUMBER 37550 CO 2515/109 TI 37550 CO N/A 83750 CO 84750 CO 92904 RI 92720 RI 84750 CO 81700 CO 82701 CO TITLE Engineering (Visit ¹3)
MOV Testing - Generic Letter 89-10 Engineering (Visit ¹4)
Initial Operator Exams Occupational Radiation Exposure (Outage Unit 1)
Radioactive Waste Treatment and Effluent and Environmental Monitoring (Effluents)
Followup - Radiological Controls Corrective Action Radioactive Waste Treatment and Effluent and Environmental Monitoring (Environs Monit)
Physical Security Program for Power Reactors Operational Status of the Emergency Preparedness Program DATE 9/23/96 9/23/96 3/10/97 10/21/96 9/9/96 2/24/97 3/3/97 Est.
3/3/97 Est.
4/21/97 11/4/96 1/13/97 Inde endent S ent Fuel Stora e Installation ISFSI Ins ections IP NUMBER 60851 60852 TITLE Design Control of ISFSI Components ISFSI Component Fabrication by Outside Fabrications DATE TBDN TBD" 60853 On-Site Fabrication of Components and Construction of an ISFSI TBD%
60854 60855 37828 Preoperational Testing of an ISFSI Operation of an ISFSI Installation and Testing of Modifications TBDk TBD" TBD" "Note: Inspection dates to be determined based on progress of the ISFSI project