ML20203N164
| ML20203N164 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/17/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20203N160 | List: |
| References | |
| NUDOCS 8609230176 | |
| Download: ML20203N164 (4) | |
Text
'o UNITED STATES 8
g NUCLEAR REGULATORY COMMISSION o
O E
WASHINGTON, D. C. 20555 5
\\.../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.47TO FACILITY OPERATING LICENSE DPR-77 AND AMENDMENT NO.39TO FACILITY OPERATING LICENSE DPR-79 TENNESSEE VALLEY AUTHORITY INTRODUCTION On February 21, 1985, the NRC staff issued a safety evaluation report (SER) on a topical report prepared by the Westinghouse Owners Group (WOG) and titled,
" Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System," WCAP-10271, February 3,1983 (as supplemented October 4,1983). This report set forth the methodology employed by WOG to justify proposed revisions to generic and plant specific technical specifications. The revisions were related to increasing surveillance intervals and out-of-service times for tech na and maintenance of the Reactor Trip System (RTS).
~
The staff's safety evaluation of WCAP-10271 co eluded that the report, along with the staff's independent analysis, presented an acceptable basis for allow-ing approval of the following plant specific technical specification changes:
(1)
Increase in surveillance interval for RTS analog operational tests from once per month to once per quarter (2) Increase the time which an inoperable RTS analog channel may be main-tained in an untripped condition from one hour to six hours (3)
Increase the time an inoperable RTS analog channel may be bypassed to allow testing of another channel in the same function from two hours to four hours. Also, the channel test may be done in the bypass mode leaving the inoperable channel in a tripped condition (4) Allow testing of RTS analog channels in a bypassed condition instead l
of a tripped condition.
By letter dated May 23, 1986, the Tennessee Valley Authority submitted a license amendment request which proposed revisions to the technical specifications of the Sequoyah Nuclear Plant, Units 1 and 2.
This request proposed extending l
8609230176 860917 PDR ADOCK 05000327 P
surveillance frequencies and out of service times for the RTS (WCAP-10271) as well as changes to the technical specifications in response to Generic Letters (GL's)83-28and85-09. The request also included editorial changes and a change to effect confonnance to the Westinghouse Standard Technical Specifications.
The following safety evaluation addresses all the proposed changes except those related to G.L. 83-28 and G.L. 85-09.
EVALUATION The licensee's proposed changes to the technical specification and staff's evaluation are itemized below.
i Change No. 1 - Licensee proposes to change Action Statements No. 2a, No. 6a, and No. 13. Table 3.3-1 of Unit I and Unit 2 Technical Specifications to extend, from one to six hours, the time an inoperable channel may be in an untripped condition. This change is acceptable in that it is consistent with the ap-proved changes as set forth in staff's February 21, 1985, SER on WCAP-10271.
Changa No. 2 - Licensee proposes to change Action Statements Nos. 2b and 6b of Table 3.3-1 of Unit 1 and Unit 2 Technical Specifi-cations to extend from two to four hours, the time an inoperable channel may be bypassed for surveillance testing.
l This change is acceptable because it is consistent with ap-proved changes as set forth in staff's February 21, 1985, SER l
on WCAP-10271.
Change No. 3 - The licensee proposes to change Action Statement No. 7 of Table 3.3-1 of Unit 1 and Unit 2 Technical Specifications to extend from one to six hours, the time in which an in-operable channel may be in an untripped condition. The staff finds this change acceptable based on its similarity to re-quested changes to Action Statements 2a and 6a.
Change No. 4 - Licensee proposes to delete Action Statements 9, 10, and 11 of Table 3.3-1 and Note 3 of Table 4.3.2 for both Units 1 and 2 Technical Specifications. NUREG-0452 " Westinghouse Standard Technical Specifications for Pressurized Water Re-actors" indicates that Action Statement No. 9 applies to N-1 loop operation (for Sequoyah, this translates to three-loop operation). Since Sequoyah is not licensed for N-1 loop operation, the staff agrees that Action Statement No. 9 has no applicability to the plants' Technical Specifications.
Action Statecient No. 9 may, therefore, be deleted without having any adverse impact on the quality of the plants' Technical Specificatiops.
Action Statement No. 10 describes two steps to be taken should the minimum 4perable channel requirements not be t
met for the reactor coolant pump breaker position trip.
Operation pursuant to Action Statement No. 10 directives, may be continued in accordance with Action Statement 11.
The presence of Action Statement-10 and.11 appears to be inadvertent since the reactor coolant pump breaker position trip is not included among the listed trips in the reactor protection system. Further, there is no other reference to these statements elsewhere in the body of the table.
Therefore, staff has no objection to their deletion, since deletion amounts to only an editorial change.
Note No. 3 of Table 4.3.2, describes the type of procedure to be implemented during the channel functional test by calling for the application of either vacuum or pressure to the appropriate side of the channel transmitter. This note is not referenced in the body of Table 4.3.2.
Like-wise NUREG-0452 excludes this notation from the standard Table 4.3.2.
The staff's view is that this note may, there-fore, be deleted without any adverse impact on the Sequoyah Technical Specifications.
Change No. 5 - Licensee requests the extension of the surveillance intervals for functional testing of Engineered Safety Features Manual Actuation channels (Table 4.3-2) from monthly to once each 4
refueling outage (18 months). The staff finds this request acceptable because the surveillance interval requested by licensee is the same as that allowed in the Connission's i
" Standard Technical Specifications for Westinghouse Pres-surized Water Reactors," Revision 4, NUREG-0452. Because of this change, the licensee can delete the original Note 1 from Table 4.3-2 since this note was needed for the monthly checks only.
This SER addresses only change requests which are related to the approved changes of WCAP-10271, editorial changes, and changes which effect conforinance to the l
Standard Technical Specification. Other change requests identified in licensee's submittal are related to G.L. 83-28 and 85-09 and will be addressed in another safety evaluation.
The staff finds acceptable the proposed Technical Specification changes related to extending surveillance interval and out-of-service times for testing and maintenance of the Sequoyah Unit 1 and 2 Reactor Trip System and the other changes as described above.
III. ENVIRONMENTAL CONSIDERATION 1
These amendments involve changes in surveilJance requirements. The staff has deterinined 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 Connission has previously issued a proposed i
I finding that these amendments involve no significant hazards con?ideration, and there has been no public comment on such finding. Accordingly, the amendments i
meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
IV. CONCLUSION The Commission made a proposed determination that the amendments involve no significant hazards consideration which was published in the Federal Register on July 2,1986 (51 FR 24264) and consulted with the state of Tennessee.
No public comments were received, and the state of Tennessee did not have any comments.
a We have concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the connon defense and security or to the health and safety of the public.
Principal Contributors: Carl R. Stahle, PWRf4, DPWR-A Joe Holonich, PWRf4, DPWR-A E. Fields, EICSB Dated:
september 17, 1986 i
l I
e e
.