ML18153A447
| ML18153A447 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna |
| Issue date: | 10/01/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML18153A446 | List: |
| References | |
| NUDOCS 9710060213 | |
| Download: ML18153A447 (2) | |
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e UNITED STATES NUCLEAR REGULATORY COMMISSION WASHIN_GTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST FROM THE IMPLEMENTATION OF 10 CFR 50.55a REQUIREMENTS VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION CSPS). UNIT 1 AND 2 AND NORTH ANNA POWER STATION (NAPS), UNIT 1 AND 2 DOCKET NOS. 50-280, 50-281, 50-338 AND 50-339
1.0 INTRODUCTION
In a Federal Register notice dated August 8. 1996 (61 FR 41303). the Nuclear Regulatory Commission amended its regulations to incorporate by reference the 1992 Edition of Subsections IWE and IWL of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code into 10 CFR 50.55a. "Code and Standards." These subsections provide the requirements for inservice inspection (ISI) of Class CC (concrete) and Class MC (metallic) containments of light-water reactor plants. The effective date of the amended rule was September 9. 1996, and has expedited implementation provisions such that licensees are to incorporate the requirements into their ISI programs and complete the first containment inspection within 5 years of the effective date.
In addition. any repair or replacement activity to be performed after the effective date must be in accordance with the respective requirements of Subsection IWE or IWL.
However. a licensee may submit a request for relief from this latter requirement.
2.0 LICENSEE'S RELIEF REQUEST Virginia Electric and Power Company, the licensee of SPS and NAPS. stating that it will not have the procedures and processes established in time to fully comply with the rule within the mandated implementation date. has.
pursuant to 10 CFR 50.55a(g)6(i). requested relief of 1 year from the implementation date. September 9. 1996, of the amended 10 CFR 50.55a. until September 9, 1997. for the ASME Code requirements identified above that govern repair and replacement activities.
In the interim. the licensee continues to conduct the inservice inspection in accordance with the requirements of the 1983 (NAPS 1), 1986 (NAPS 2) and 1989 (SPS 1 & 2) Editions of ASME Code.
Section XI.
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2 3.0 STAFF EVALUATION The expedited implementation schedule of the rule and the immediate effective date for repair and replacement activities demand licensee action to develop.
and implement the new procedures and processes for the mandated program in a short time. This has presented an undue impact to the licensee's emergent work and schedule.
Repair and replacement activities are currently performed in a controlled process under work orders and maintenance procedures. Materials and work procedures are controlled under the licensee's quality assurance program.
There are no known safety concerns with the containments at Surry and North Anna which would compromise their ability to perform their intended safety functions.
All changes are to be performed in accordance with the scope of the current containment ISI and repair and replacement program. which is based on the Code edition applicable to each unit.
During the interim. while the licensee is incorporating the new requirements into the SPS and NAPS ISI programs. the programs. procedures. and processes as well as administrative procedures that are currently in place provide adequate control of design, planning. tracking and implementation of inspection of repair activities.
special processes (e.g.* welding, coating. etc.). inspection (e.g.. visual.
surface. volumetric examination). special tests (pressure tests and hydros) and disposition of nonconforming conditions and documentation of inspection.
repair and replacement activities. The quality and the safety of plants are acceptable with the existing program and will not be compromised in the interim before the new procedure will be developed and implemented by September 9. 1997.
3.0 STAFF CONCLUSION Based on the review of the relief request. it is acknowledged that the immediate implementation of the requirements of the 1992 Edition of the ASME Code for repair and replacement activities at Surry and North Anna. as required by 10 CFR 50.55a. will result in hardship for the licensee. The staff finds that the use of the respective editions of the ASME Code and the associated quality assurance requirements. as supplemented by the site-specific quality assurance program developed by the licensee. provide an acceptable level of safety and quality in the interim. Accordingly, the licensee's relief request for delayed implementation of 10 CFR 50.55a is acceptable. pursuant to 10 CFR 50.55a(a)(3)(i). until September 9. 1997.
Principal Contributor:
Chen P. Tan Date: October 1, 1997