ML20239A648

Forwards SALP Input for Facility Licensing Activities for Jan 1986 - Jul 1987.Rept Based on Inputs Provided by NRR Reviewers & Observations by Project Managers During SALP Period

ML20239A648
Person / Time
Site:	Summer
Issue date:	09/16/1987
From:	Hopkins J Office of Nuclear Reactor Regulation
To:	Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8709180050
Download: ML20239A648 (5)

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September 16, 1987 c.- vic ]

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1 MEMORANDUM FOR: Luis.A. Reyes, Director l'TSTRIBUTION Division of Reactor Projects, RII.- M, Noett.a PD21 , ,'f THRU: . Elinor G. Adensam, Director JHopkins 2 Project Directorate 11-1 Division of. Reactor Projects I/II, NRR

-FROM: Jon~ B. Hopkins, Project Manager i Project Directorate.II-1 l Division of Reactor Projects I/II, NRR

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SUBJECT:

NRR SALP INPUT FOR V. C. SUMMER, 1/1/86 THROUGH l

'7/31/87. l Enclosed is NRR's SALP input for the V. C. Summer Nuclear Station covering ,

South Carolina Electric and Gas Company (SCE&G) licensing activities for the period from January 1, 1986 thr.ough July 31, 1987. The report is based  !

on inputs provided by NRR reviewers and observations by NRR project manage- I ment during their interactions with SCE&G during the SALP period. A perfor-mance rating of Category-2 has been assigned by the NRR SALP evaluation 3 effort for the current rating period.

S Jon B. Hopkins, Project Manager Project Directorate 11-1 1 Division of Reactor Projects I/II, NRR

Enclosure:

As Stated i

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( JHopkins/dsf sam EAdep/87 9/J)

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0FFICE OF NUCLEAR REACTOR REGULATION INPUT FOR SALP REPORT I

SOUTH CAROLINA ELECTRIC AND GAS COMPANY  !

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V. C. SUMMER NUCLEAR STATION

1. Licensing Activities: January 1, 1986 - July 31, 1987 1

This report documents NRK input to the Systematic Assessment of Licensee Perfonnance (SALP) report for the V. C. Summer Nuclear Station. The assessment of licensee perfonnance was conducted pursuant to NRR Office l Letter No. 44, Revision 1 "NRR Inputs to SALP Process," dated December  !

22, 1986. Office Letter 44, Revision 1, incorporates NRC Manual Chapter i 0516. " Systematic Assessment of Licensee Performance."

The basis for this appraisal was the licensee's performance in support of licensing activities (amendment requests, responses to generic letters, and other actions) which have been reviewed and evaluated by the staff during the rating period. The subjects involved are listed in Attachment 1.

In general, management involvement has been constant over the report j l

period. Management has continued an active role in major issues such as l l

steam generators and fire protection. Management requested a meeting with NRR senior management (post NRC reorganization) to discuss management 1

' issues. Licensing management has demonstrated prior planning and involve-

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ment in both site activities and licensing activities; however, four needed license amendments were requested within 3 months of the start of the last refueling outage. More planning should be done in order to submit licensing l j

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-2 actions needed for'an outage in a more timely manner. Involvement in assuring quality is apparent from the technical soundness of most reviews performed. Examples of quality submittals are the boron concentration and i

ESF response time submittals. That level of quality should be maintained for future submittals. The licensee's determinations regarding no significant hazards considerations have uniformly improved and are gen- j erally of good quality. '

The licensee has been very responsive to NRC initiatives. The licensee  !

provided a prompt and complete response to the NRC request for information '

regarding documentation of implementation of approved regulatory improve-ments. Also, the licensee was extremely cooperative with the NRC control room habitability survey. The licensee's responsiveness to the staff's requests for additional infonnation has been prompt for plant specific and most generic issues; however, a response on the generic issues regarding relief and safety valves has not been prompt. The licensee keeps the Project Manager informed on status of ongoing activities and has taken the initia-tive in discussions and meetings on ongoing licensing activities.

The licensee continues to keep informed of industry approaches to plant safety issues and is aware of programs, problems and resolutions thereto, at other plants. The licensee accomplishes this by membership in major industry advisory groups and, particularly, by membership in owners groups.

The licensee recently joined EPRI. This additional membership should

l enhance their knowledge of generic issues affecting the electrical i

power industry.

The licensee is generally timely in reporting operational events. Their i Licensee Event Reports (LERs) are timely and complete in general. However, some improvement is needed on the LER reports, because the NRC staff feels that they are a little below the industry average.

Conclusions and Recommendations .

An overall performance rating of Category 2 has been assigned by NRR for the i

SALP evaluation over the current rating period in the specific area of licensing

. activities. NRR recommends that SCE&G management attention be increased in the area of written reports.

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Attachment 1 Licensing Activities i

The assessment on licensing activites was based on licensing actions which included the following: l l

Salem ATWS Item 1.2, Post-Trip Review

• Salem ATWS Item 2.1, RTS Components Classification and Vendor Interface t

• Salem ATWS Item 3.2.1 and 3.2.2, Post Maintenance Testing,. safety related components

• Salem ATWS Items 4.1.2 & 4.2.2, Preventive Maintenance RTBs Response to Pressurized Thermal Shock (PTS) Rule, 10 CFR 50.61 NUREG-0737. Item II K.3.31, Compliance with 10 CFR 50.46 j Diesel Generator Reliability  ;

I Iodine Spikes, removal from TS, GL85-19 ASME Section XI Relief i

Fire Protection Reanalysis License Amendments Issued (nineteen) ,

1 Significant Amendments included: i

~* Steam Generator Tube Analysis & Sleeving  !

Pressure / Temperature Limits Fuel Assembly TS  ;

Fission Chamber Detectors ESF Response Times Boron Concentrations f RCS Flow Measurement Uncertainty Heat Flux Hot Channel Factor

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