ML20044A764
| ML20044A764 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 06/27/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20044A761 | List: |
| References | |
| NUDOCS 9007020203 | |
| Download: ML20044A764 (3) | |
Text
.
omu g[. 3 -q UNITED sT ATES
',3 NUCLE AR REGULATORY COMMISSION W A&HING T ON, 0. C. 20bbb k.....
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 24 TO FACILITY OPERATING LICENSE NO. NPF 72 AND AMENDMENT NO. 24 TO FACILITY OPERATING LICENSE NO. NPF-77 COMMONWEALTH EDISON COMPANY BRAIDWOOD STATION, UNIT NOS. 1 AND 2 DOCKET NOS. STN 50 4F6 AND STN 50-457
1.0 INTRODUCTION
By letter dated August 14, 1989, and supplemented by letter dated March 19, 1990 Commonwealth Edison Company (Ceco), the licensee, submitted proposed amendments to Facility Operating Licenses NPF-72 and NPF-77, for Braidwood Station, Units 1 and 2.
The proposed amendments request a change to Technical Specification (TS) 6.2.3.2 to reduce the number of members of the Onsite NuclearSafetyGroup(ONSG)fromfourmemberstothreemembers.
2.0 DISCUSSION The ONSG performs the functions defined in NUREG-0737, item 1.B.1.2 -
IndependentSafetyEngineeringGroup(ISEG).
This item was developed by the NRC staff as part of the Action Plan which was issued after the accident at Three Mile Island, Unit 2, to improve safety at power reactors.
As stated in NUREG-0737, Item 1.B.1.2:
i "The principal function of the ISEG is to examine plant operating characteristics, NRC issuances, licensing Information Service advisories, and other appropriate sources of plant design and operating experience information that may indicate areas for improving plant safety. The ISEG is to perform independent review and audits of plant activities including maintenance, modifications, operational problems, and operational analysis and aid in the establishment of programmatic requirements for plant activities."
"Another function of the ISEG is to maintain surveillance of plant operations and maintenance activities to provide independent verification that these activities are performed correctly and that human errors are reduced as far as practicable.
ISEG will then be in a position to advise utility management on the overall quality and safety of operations."
$$[0$$hN $$Nn6 p
6 e
, l in NUREG 0800, Section 13.4, item !!.3.b., it is further stated *That l
groupshallbecomprisedofaminimumoffivededicated,fulltImeengineers, i
located onsite, but reporting offsite to a corporate official who holds a high-level, technically oriented position who is not in the management chain for power production.
For utilities with multiple sites, it may be possible to perform portions of the independent safety assessment function in a i
centralized location for all the utility's slants.
in such cases, an onsite group is still required, but it may be sligitly smaller than would be the case if it were performin For example,theISEGforTVAgtheentireindependentsafetyassessment."
s Sequoyah plants has been authorized by the NRC staff to be composed of three members.
Additionally, this amendment request was approved by the NRC staff for the Byron Station on July 1,1988.
CECO has two additional organizations which perform an independent review and audit function.
The Onsite Quality Assurance Group performs audits and surveillances of various production activities and are independent of the production function. The Licensing and plant Support Services Group (LPSSG) reports to the Senior Vice President of Nuclear Operations as does i
the Vice President for PWR operations.
This LPSSG has both onsite and offsite elements which monitor station performance, conduct technical assessments, cocrdinate off-normal event investigations, and implement regulatory performance improvement and trending programs. The information obtained by these two groups is shared with ONSG and is utilized by the i
ONSG in performing its review and audit functions.
l Thus, many of the functions that NUREG 0737, item 1.B.1.2, requires of the ONSG are being accomplished by the Onsite Quality Assurance Group and the LPS$G.
The mission of the ONSG can be accomplished more efficiently by using the data and reports generated by these two other groups.
Based on this, and based on the licensee's ability to supplement the ONSG personnel i
with engineering personnel from the corporate nuclear safety staff, the NRC staff concludes that reducing the ONSG to three members is acceptable.
3.0 [NVIRONMENTAL CONSIDERATIONS This amendment relates to changes in recordkeeping, reporting, or administrative procedures or requirements.
Accordingly, this amendment meets the elig)ibility criteria for categorical exclusion set forth in 10CFR$1.22(c(10). Pursuantto10CFR51.22(b)noenvironmentalimpact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
The NRC staff has further concluded based on the considerations discussed above, that:
(1)thereisreasonableassurancethatthehealthandsafety l
)
j
D 3
of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regult.tions, and (3) the issuance of this amendment will not be inimical to the common defense an( security or health and safety of the public.
principal Contributor:
Stephen p. Sands Dated: June 27, 1990
.e e
)