ML20114A734

From kanterella
Jump to navigation Jump to search
Safety Evaluation Supporting Amend 153 to License DPR-46
ML20114A734
Person / Time
Site: Cooper Entergy icon.png
Issue date: 08/12/1992
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20114A733 List:
References
NUDOCS 9208200268
Download: ML20114A734 (3)


Text

,

\\

/remov,).

D)%i NUCLEAR REGULATOR'/ COMMISSION y

UNITED STATES E,

8 WASHINGioN. D C. 20te25 o

/

SAFETY EVALVATION BY THE OFFIN OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. M3 TO FAClllTY OPERATING LICENSE N0. DPR-46 NEBRASKA PUBLIC POWER D15110.01

[00PER NVCLEAR STATION DOCKET NO. 50-298 1.0 INTRODJICTION By letter dated June 16, 1988, Nebraska Public Power District (the licensee) submitted a request for changes to the Cooper Nuclear Station (CNS) Technical Specifications (TS).

The requested changes would incorporate requirements for the use of redundant channels of oxygen monitoring in the primary containment atmosphere and several administrative changes associated with their installation and use.

2.0 [yALVATION In the current CNS TS, only one analyzer for measurement of oxygen concentration in the primary containment is specified. To meet the guidance contained in Regulatory Guide 1.97 regarding redundant channels that meet performance standards of range, seismic quality, environmental qualification, electrical separation, and post-accident performance capabilities, new oxygen analyzing instrumentation has been installed.

The new instrumentation was installed as part of an integrated H /0 analyzer system.

Each channel of the z 2

ystem consists of an analyzer panel and micropro;essor controls, along with the necessary recording equipment and plant process computer outputs.

Each channel is powered by a separate division of power.

The change replaces the old oxygen analyzer, having identification number PC-0 A-512, with two new channels of analyzers, PC-AN/CS-H,/0 A and PC-A,N/CS-H /0 B.

THI Action Plan Requirements in NVREG-0737 require that the 2

2 2 hydrogen / oxygen instrumentation for indication and re:ording be functioning within 30 minutes of the initiation of safety injection.

By letter dated July 21, 1992, the licensee confirmed that this requirement is met.

The staff finds that the proposed change is consistent with current regulatory guidance, is appropriate for the intended purpose of measuring oxygen concentration in the primary coritainment, and is acceptable.

An additional change is to remove the listing of the oxygen analyzer system l

from Tables 3.2.E and 4.2.E, which list instrumentation that monitors drywell leak detection, and enter it into Tables 3.2.F and 4.2.F, which list l

instrumentation for primary containment surveillance.

The removal of the l

[

l 9200200269 920912 l

PDR ADDCK 05000298 p

PDR

F.

. oxygen analyzer from Tables 3.2.E and 4.2.E and entry of the new instrumentation into Tables 3.2.F and 4.2.F is appropriate because of the intended function of the oxygen analyzer, and so it is acceptable.

The limiting conditions for operation and corresponding action statements in Table 3.2.F for the oxygen analyzer are consistent with the present TS requirements of Table 3.2.E and.,pecification 3.6.C.

Under current TS requirements, the single channel oxygen analyzer can be inoperable during reactor operation for periods of up to 30 days before an orderly plant shutdown is required. With the new redundant analyzers and their requirements as given in Table 3.2.F, aperation is permissible only for up to 7 days with no indication in the control room (i.e., both channels inoperable).

During

' periods when both channels are inoperable, oxygen concentration in primary containment can be measured using containment air grab samples to satisfy Specification 4.7.A.S.a for oxygen monitorirg.

The surve!11ance requirements in Table 4.2.F for primary containment oxygen analyzer are identical to those currently required by Table 4.2.E.

The changes described are appropriate to properly characterize the function of the new instrumentation and to ensure action that is appropriate to meet safety needs of operability, and are therefore acceptable.

3.0 STATE CONSUL 1AT10N in accordance with the Commission's regulations, the Nebraska State official was notified of the proposed issuance of the amendment.

The State official had no comment.

4.0- [hVIRONMENTAL CONSIDERATION The amendment changes a requirement with respect to installation or use of a facility component located within the restricted aret as defined in 10 CFR Part 20 and changes in surveillance requirements.

The NRC staff has determined that the amendment involves 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 pro-posed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (57 FR 22263).

Accordingly, the amendment meets the eligioility criteria ior categorical exclusion set forth in 10 CFR Section 51.22(c)(9).

The amendment also involtes changes in recordkeeping, reporting or administrative procedures or requirements. Accordingly, with respect to these items, the amendment meets the elig;bility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).

Pursuant to 10 CFR 51.22(b) no environmental impact-statement or-environmental assessment need be prepared in connection with the l

. issuance of the amendment.

l 1

I l-l

i

5.0 CONCLUSION

Based on the considerations discussed above, the Comission has concluded that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Comission's regulations, and (3) the issuance of the amendmer,. will not be inimical to the comon defanse and security or to the health and safety of the public.

Principal Contributor:

R. Bevan Date: August 12. 1992

_