ML20137C051
| ML20137C051 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 03/21/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20137C049 | List: |
| References | |
| NUDOCS 9703240142 | |
| Download: ML20137C051 (4) | |
Text
_
g s
y UNITED STATES
]
8
}
g j
NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 20806 0001 j
l
- SAEETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION i
RELATED TO AMENDMENT NO. 171 TO FACILITY OPERATING LICENSE NPF-9 i
AND AMENDMENT NO.155 TO FACILITY OPERATING LICENSE NPF-17 DUKE POWER COMPANY l
MCGUIRE NUCLEAR STATION. UNITS 1 AND 2 i
)
QQCKET NOS. 50-369 AND 50-370
1.0 INTRODUCTION
1 By letter dated Jauary 13, 1997, Duke Power Company (DPC or the licensee) i submitted a request for changes to the McGuire Nuclear Station, Units 1 and 2, Technical Specifications (TS). The requested changes would permit implementation of 10 CFR Part 50, Appendix J, Option B, for the Type A containment integrated leak rate tests. The TS contain a reference to Regulatory Guide (RG) 1.163, " Performance-Based Containment Leak-Test i
Program," dated September 1995, which specifies a method acceptable to the NRC for complying with Appendix J, Option B.
2.0 BACKGROUND
Compliance with 10 CFR Part 50, Appendix J, " Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors," provides assurance that the primary containment, including those systems and components which penetrate-the primary containment, do not exceed the allowable leakage rate specified in the TS and Bases. The allowable leakage rate is determined so that the leakage rate postulated in the safety analyses is not exceeded.
On February 4,1992, the NRC published a notice in the Federal _Reaister (57 FR 4166) discussing a planned initiative to begin eliminating requirements marginal to safety, which impose a significant regulatory burden. Appendix J of 10 CFR Part 50 was considered for this initiative and the staff undertook a study of possible changes to this regulation. _The study examined the previous performance history of domestic containments and examined the effect on risk of a revision to the requirements of Appendix J.
The results of this study are reported in NUREG-1493, " Performance-Based Leak-Test Program."
Based on the results of this study, the staff developed a performance-based approach to containment leakage rate testing. On September 12, 1995, the NRC approved issuance of this revision to 10 CFR Part 50, Appendix J, which was subsequently published in the Federal Reaister on September 26, 1995, and became effective on October 26, 1995.
The revision added Option B
" Performance-Based Requirements" to Appendix J to allow licensees to voluntarily replace the prescriptive testing requirements of Appendix J with testing requirements based on both overall and individual component leakage rate performance.
9703240142 970321 PDR ADOCK 05000369 P
Regulatory Guide (RG) 1.163, was developed as a method acceptable to the NRC i
staff for implementing Option B.
This regulatory guide states that the Nuclear Energy Institute (NEI) guidance document NEI 94-01, " Industry a
I Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J" provides methods acceptable to the NRC staff for complying with Option B with four exceptions, which are described therein.
Option B requires that the RG or other implementation document used by a licensee to develop a performance-based leakage rate testing program must be j.
included, by general reference, in the plant TS. The licensee has referenced j
RG 1.163 in the McGuire Nuclear Station, Units 1 and 2, TS.
l Regulatory Guide 1.163 specifies an extension in Type A test frequency to at least one test in 10 years based upon two consecutive successful tests.
i Type B tests may be extended up to a maximum interval of 10 years based upon completion of two consecutive successful tests and Type C tests may be i
extended up to 5 years based on two consecutive successful tests.
I By letter dated October 20, 1995, NEI proposed model TS to implement Option B.
After some discussion, the staff and NEI agreed on a final TS, which were attached to a letter from C. Grimes (NRC) to D. Modeen (NEI) dated November 2, 1995. These TS are to serve as a model for licensees to develop 4
plant-specific TS in preparing amendment requests to implement Option B.
For a licensee to determine the performance of each component, factors that are indicative of or affect performance, such as an administrative leakage limit, must be established. The administrative limit is selected to be indicative of the potential onset of component degradation. Although these limits are subject to NRC inspection to assure that they are selected in a reasonable manner, they are not TS requirements.
Failure to meet an administrative limit requires the licensee to return to the minimum value of the test interval.
Option B requires that a licensee maintain records to show that the criteria for Type A, B, and C tests have been met.
In addition, a licensee must maintain comparisons of the performance of the overall containment system and the individual components to show that the test intervals are adequate.
These records are subject to NRC inspection.
3.0 EVALUATION The proposed amendments would replace the prescriptive Type A containment leakage rate testing requirements of 10 CFR Part 50, Appendix J, with the performance-based requirements of the revised Option B of Appendix J.
This requires changes to existing TS as discussed in detail below.
Correspondir.g Bases were also modified.
4
- O l
1 3-q The proposed amendments meet the particular requirement of Option 8 that the implementation document used by the licensee to develop a performance-based leakage rate testing program must be included, by general reference, in the plant TS by including RG 1.163 in TS 4.6.1.2.
This guide specifies a method acceptable to the NRC for complying with Option B.
TS 4.6.1.2 is modified to require that the containment leakage rates shall be demonstrated in accordance with a test schedule determined in conformance with Appendix J, Option B, using the methods and provisions of RG 1.163, i
TS 3.6.1.2.a and its corresponding ACTION statement, TS 4.6.1.2.f, and TS 4.6.1.2.h have been modified by deleting the provisions to conduct Type A integrated leak rate testing (CILRT) at a reduced pressure since reduced l
pressure testing is not included in the revised Appendix J, Option B rule.
The Surveillance Requirements in TS 4.6.1.2.a and b. have been deleted because their provisions have been superseded by the modified requirements of l
Option B.
TS 4.6.1.2.c has been modified such that the accuracy of each Type A test i
shall be verified by a supplemental test in accordance with RG 1.163.
TS 4.6.1.2.d provides clarification that Type B and Type C tests wil continue l
to be performed according to the provisions of 10 CFR 50.54(o) and 10 CFR 50 1
Appendix J, Option A.
l TS 4.6.1.6 and 4.6.1.7 have been modified such that the current frequency of conducting the visual inspections of the containment vessel and the reactor building of three times per 10-year interval will be maintained. This is 4
consistent with the guidance of RG 1.163, Position 3, and is acceptable.
Appendix J, Option B permits a licensee to choose Type A; or Types B and C; or i
Types A, B, and C testing to be done on a performance basis. The licensee has l
elected to perform the Type A testing on a performance basis. The licensee has not proposed to perform the Type B and Type C tests in accordance with Option B at this time.
l i
The TS changes proposed by the licensee are in compliance with the
{
requirements of Option B and consistent with the guidance of RG 1.163, and the model TS of the November 2, 1995, letter and are, therefore, acceptable to the j
staff.
1
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the North Carolina State i
official was notified of the proposed issuance of the. amendments. The State official had no comments.
i N
l i
e d
,c..
=r r----
- o
' l
5.0 ENVIRONMENTAL CONSIDERATION
s 1
The amendments change requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR l
Part 20 and change surveillance requirements. Tne NRC staff has determined i
that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a l
proposed findin consideration, g that the amendments involve no significant hazards and there has been no public comment on such finding (62 FR 6575 dated February i
12,1997). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR
{
51.22(c) 9).
environme(ntal assessment need be prepar(ed in connection with the 1
the amendments.
1
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safet public will not be endangered by operation in the proposed manner,y of the j
activities will be conducted in compliance with the Commission's reg (2) such
- ulations, and (3) the issuance of the amendments will not be inimical to the common 4
defense and security or to the health and safety of the public.
1 i
1 Principal Contributor: S.S. Kirslis Date:
March 21, 1997 i
f 1
i l
4 f
a i
i i
4 1
e