ML17300A809
| ML17300A809 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 05/04/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17300A807 | List: |
| References | |
| GL-83-28, NUDOCS 8705070256 | |
| Download: ML17300A809 (6) | |
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ENCLOSURE.2 SAFE:jY EVALUATION REPORT PALO VERDE NUCLEAR GENERATING STATION UNITS 1
2 AND 3 EACTOR TRIP SYSTEH RELIABILITY ITEMS 4.2.3 AND 4.2.4 OF GENERIC LETTER 83-28 1.
INTRODUCTION On July 8,'1983, the Nuclear Regulatory Comm1ssion (NRC) 1ssued Generic Letter (GL) 83-28.
This letter addressed 1ntermediate-term act1ons to be taken by 11censees and applicants a1med at assuring that a
comprehens1ve program of prevent1ve maintenance and surveillance test1ng is implemented for the reactor trip breakers (RTBs) 1n pressurized water reactors.
In part1cular, Item 4.2 of the letter requ1red tpe 11censees and applicants to subm1t a descr1pt1on of their preventive maintenance and surveiTlanc> 'program to ensure rel1able reactor trip breaker operat1on.
The descript1on of the submitted program was to 1nclude the following:
GL, Item 4.2.3 L1fe testing of the breakers (1nclud1ng the tr1p attachments) on an acceptable sample s1ze.
GL, Item 4.2.4 Periodic replacement of breakers or components consistent with demonstrated 11fe cycles.
Arizona Public Serv1ce
- Company, the appl1cant for Palo Verde, Un1ts 1, 2 and 3, submitted a response to Items 4.2.3 and 4.2.4 of the Gener1c Letter on November 5,
1983.
Th1s report presents a'n evaluation of the adequacy of that response and of the applicant's 11fe testing and period1c replacement programs for RTBs.
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2.
EVALUATION CRITERiA 2.l Life Test1n Pro ram L1fe test1ng of the RTBs 1s spec1f1ed by Item 4.2.3 of the Gener1c Letter.
The purpose of the 11fe testing is to 1dentify a qualitied 11fe
'or the breaker{s) or any of 1ts replaceable components.
If it can be demonstrated that the qual1f1ed 11fe exceeds the 11fe of the Generating Stat1on then the specif1c qual1f1ed 11fe need not be 1dent1f1ed.
2.2 Per1odic Re lacement Pro ram t
If the qualif1ed life of any component is less than. the qualified life of the RTB,'hen the component should be replaced on an appropr1ately shorter time schedule.
The, criteria developed 1n support of th1s 1tem 1nclude record keep1ng for serv1ce t1me and number of cycles for all breakers and short-11ved dev1ces or components.
3.
EVALUATION 3.1 Evaluation of the A
11cant's Pos1t1on on Item 4.2.3 The applicantls response identified the life test program for both of the Reactor Trip Breakers (General Elect ic Model AKR-30 and Westinghouse Type OS-206) used at Palo Verde.
On-site review of that program (Reactor Trip Switchgear System Equipment Environmental gualification Program No.
14723-ICE-3516, Rev. 3, dated 1/29/85) on June 12, 1986, by the staff and its contractor, INEL, determined that it satisfactorily addressed establishment of both mechanical (cycling) and non-mechanical (age-related) life limiting phenomena for the RTBs, and that it documents the results of the life test program.
The staff finds that the appl1cant's 11fe test1ng pIogram has satisfactorily established the breakers'ualified l1fe.
It
3.2 Evaluat1on of the A
11cant's Pos1t1on on Item 4.2.4 The appl1cant's 11fe test program has estab11shed per1od1c replacement 1ntervals for component's of the RTBs w1th a qual1f1ed 11fe less than that of the breakers themselves.
The staff f1nds the appl1cant's per1od1c replacement program to be acceptable, and that the program 1s suff1c1ent to detect breaker degradat1on and prov1des a h1gh degree of conf1dence that the reactor tr1p breakers w1ll perform the1r safety funct1on when requ1red.
4.
CONCLUSIONS Based on a rev1ew of the appl1cant response and an on-s1te rev1ew of the appl1cant's l1fe qual1f1cat1on
- program, the staff f1nds the appl1cant's posit1on on Item 4.2.3 and. 4.2.4 of Gener1c Letter 83-28 to-be acceptable.
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