ML18004B897
| ML18004B897 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 07/28/1987 |
| From: | Buckley B Office of Nuclear Reactor Regulation |
| To: | Congel F, Partlow J, Rossi C, Shao L, Varga S Office of Nuclear Reactor Regulation |
| References | |
| TASK-2.K.3.05, TASK-2.K.3.30, TASK-2.K.3.31, TASK-TM GL-83-28, NUDOCS 8707310117 | |
| Download: ML18004B897 (6) | |
Text
MEMORANDUM FOR:
Steven A. Varga, Director DISTRIBUTION:
Dill fR t
P Iill '~3 NRC PDR Lawrence C. Shao, Director Local PDR Division of Engineering G. Lainas and Systems Technology B. Buckley P. Anderson Charles E. Rossi, Director PD21 r/f Division of Operational Events Assessment Frank J. Congel, Director Division of Radiation Protection and Emergency Preparedness James G. Partlow, Director Division of Reactor Inspection and Safeguards THRU:
FROM:
Elinor G. Adensam, Director Project Directorate II-1 Division of Reactor Projects I/II Bart C. Buckley, Senior Project Manager Project Directorate II-1 Division of Reactor Projects I/II Enclosed is a draft of NRR's SALP input for Shearon Harris Nuclear Power Plant, Unit 1, covering Carolina Power 5 Light Company (CP8L) licensing activities for the period from August 1, 1986 through June 30, 1987.
The report is based on inputs provided by NRR reviewers and observations by NRR project management during their interactions with CPIIL during the SALP period.
A per-formance rating of Category 1 has been assigned by the NRR SALP evaluation effort for the current licensing period.
Please review the draft assessment and provide any comments you feel are appro-priate.
All comments received by July 31 will be considered for incorporation in the final report.
Due to the short time alailable for comment, please provide your comments directly to the Harris Project Manager, Bart Buckley, at X27215.
The NRC SALP Board meeting for Shearon Harris is scheduled for August 27, 1987.
Enclosure:
Draft NRR SALP Report Bart C. Buckley, Senior Project Manager Project Directorate II-1 Division of Reactor Projects I/II PM:PD21:DRPR BBuckley 7/g.
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 OFFICE OF NUCLEAR REACTOR REGULATION INPUT FOR SALP REPORT CAROLINA POWER 8
LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 Licensin Activities (Au ust 1
1986 to June 30 1987 The basis for this appraisal was the licensee's performance in support of licensing actions (Low power license, full power
- license, amendment requests and other actions) which have been reviewed and evaluated by the staff during the rating period.
The activities associated with this rating period include those in the prelicensing period (August-October, 1986) which culminated in the issuance of a low power license and those associated with the issuance of a full power license are identified below to reflect the transitional aspects of this licensing application.
The low power and full power licenses were issued in October
- 1986, and January 1987, respectively.
The various issues involved include the following:
Plant S ecific Issues resolved in su ort of low ower license (1)
Effect of local intense precipitation 2)
Normal water supply 3)
Emergency water supply 4
Technical Specifications and emergency operating requirement 5
Instrumentation (6
Moderator temperature coefficient (7)
Crud deposition 8
Pressurized thermal shock 9
Residual heat removal system
- 10) Containment isolation system (ll) Large-break LOCA 12 Small-break LOCA 13 Control room habitability 14 Spare component cooling water (CCW) pump (15) Spare charging pump (16) Electric power systems 17)
AC power system
- 18) Physical independence of redundant safety-related systems (19)
TMI Action Plan requirements
- 20) Primary component cooling water system 21 Essential services chilled water system 22 Emergency diesel engine fuel oil storage and transfer system 23 ECCS leakage outside containment 24 Generic Letter 83-28 (Revi si on 0)
2>>
(Revision 0)
(25) II.K.3.30, Revised small-break LOCA methods to show compliance with 10 CFR 50.46 (26) II.K.3.31, Plant-specific calculations to show compliance with 10 CFR 50.46
- 27) Organization
- 28) Building clearances Plant S ecific Issues resolved in su ort of full ower license (I)
Emergency Diesel Generator Reliability (2)
Physical Independence of Redundant Safety-Related Systems (3)
Emergency Planning (4)
Operating and Maintenance Procedures (5)
Preoperational Test Program (6)
II.K.3.5, Automatic Trip of RCPs during LOCA (7)
Technical Specifications Management continues to exercise control and overview in the licensing activity area as evidenced by the very successful manner in which the various issues associated with the preparation of both the low power license and full power license Technical Specifications were resolved.
The licensee's management continued to take a strong and aggressive approach in resolving various technical issues which resulted in the very timely resolution of all issues necessary to support the issuance of a low power license in October 1986, and a full power license in January 1987.
The licensee's computer system, which keeps abreast of all issues requiring resolution, contributed significantly to the effective management of licensing activities.
The licensee's management demonstrated a good understanding of the various technical and licensing issues.
Licensing personnel who are generally in daily contact with the NRC licensing project manager have an excellent understanding of the technical and licensing issues.
Monthly meetings are generally held with the NRC staff to discuss scheduling and prioritization of licensing activities.
The licensee's amendment requests have been submitted in a very timely manner indicating the licensee's sensitivity to allow appropriate lead time for NRC staff review.
Moreover, while there have only been a limited number of amendment
- requests, the NRC licensing project manager is always informed by the licensing personnel of the pending amendment request several weeks in advance of its submittal.
This enhances the overall management and the scheduling of licensing activities.
The licensee's involvement in the preparation of the low power license and full power license Technical Specifications was outstanding as was the effort in resolving the various licensing issues in support of the issuance of the above cited licenses and is indicative of the strong and aggressive approach that is taken to resolve issues.
Throughout the period of Technical Specifications development the licensee had exhibited a very straightforward attitude and provided rapid responses to questions raised by the staff.
(Revision 0)
The licensee's response to NRC initiatives is prompt and generally complete.
The licensee's continued involvement in a significant number of utility advisory and owners groups is indicative of their commitment to be aware of the methods of timely resolution of issues of. a generic nature such as the issue on Transamerica Delaval diesel generators..
Daily communication between the licensee staff and the NRC Licensing Project Manager continues to yield timely and sound technical responses to NRC initiatives.
An example of this initiative is the detailed presentation by the licensee, as requested by staff, on the root causes of balance-of-plant initiated trips and the planned corrective actions to minimize p'lant trips.
It should also be noted that the licensee voluntarily made available to the NRC staff its evaluation of the perfor-mance indicators for the Shearon Harris plant and its comparison with other Westinghouse near-term operating license plants (NTOLs).
The licensee has adequate licensing staff who have a solid working knowledge of the regulations,
- guides, standards and generic issues as they apply to the Shearon Harris facility.
One of the licensing staff is Chairman of the Westinghouse Owner s Group Technical Specification Subcommittee coordinating the Technical Specification Improvement Program.
The assignment of certain licensing personnel at the site in conjunction with the coordination with the off-site licensing staff has continued to result in prompt and timely responses to the NRC staff needs in the area of licensing.
The licensee promptly notified the NRC Licensing Project Manager of operational events generally after they evaluated the cause of the ev'ent.
There has been a significant number of malfunctions of the plant computer security system during the first three or four months following the issuance of the Low power license.
Subsequently, a steering committee was established by the licensee to evaluate the security computer problems.
As a result of committee efforts and corrective measures taken there has been a large reduction in the number of security computer malfunctions.
The number of scrams initiated by the secondary system is higher than those experienced at other Westinghouse NTOLs.
The licensee formed a task force, which included various technical disciplines, and conducted a
comprehensive evaluation of the cause of the secondary system trips, and as a result of this effort certain modifications or adjustments have been made to reduce the likelihood of plant trips.
The Licensee is presently continuing this effort over the long term to determine what other steps may be taken to further minimize secondary system initiated trips.
License Event Reports (LERs) are submitted on a timely basis and contain a detailed description of the event and its evaluation.
A plant specific simulator is operational and is being used in the training of new operating personnel and in the requalification of licensed operators to effectively maintain plant safety.
The Senior Vice President Operations Support Group and the Manager of Licensing and Nuclear Fuels receiv'ed training using the simulator.
~ 4 P
(Revision 0) 2.
Conclusion 3.
An overall performance rating of Category 1 has been assigned for the functional area of Licensing Activities for this raking period.
Other Functional Areas The Licensee's performance in resolving certain allegations contained in a 2.206 petition was very commendable.
In the area of house-
- keeping, good cleaning practices are being maintained throughout the plant including the control room.
RECORDS OF MEETINGS AND OFFICIAL DOCUMENTS 2.
Si nificant NRR/Licensee Meetin s
There were four significant meetings between the licensee and NRR during this rating period.
Three of these meetings were he'ld to discuss schedular and prioritization of licensing activities and one was a Licensee management introductory meeting following the reorganization of the NRC.
NRR Site Visits PN Unescorted Access recertification 6/8/87 3.
Licensee/NRR AND Region II to discuss overall plant operations Comnission Briefin Full Power License Exem tions Granted with issuance of licenses 6/9-10/87 1/8/87 Appendix E, 10 CFR 50 Appendix J, 10 CFR 50 10 CFR 70 1/12/87 5.
Reliefs Granted 6.
relief granted from requirements for certain preservice examinations Licenses Issued 10/86 Low power license Full power license 10/24/86 Ol/12/87