ML20198L113
| ML20198L113 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/02/1986 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8606040216 | |
| Download: ML20198L113 (6) | |
Text
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[lPCtr.c aw Gis company PuLhc 5er ice E ntr c a H Gas O mpr. P O Bm '> Ha~:ov - Bodge Nj Cn038 609 339 400 Corbin A. McNeill, Jr.
v wte Press m FM Wr June 2, 1986 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention:
Ms. Elinor Adensam, Director Project Directorate 3 Division of BWR Licensing
Dear Ms. Adensam:
ELECTRICAL EQUIPMENT QUALIFICATION (LICENSE CONDITION 9)
HOPE CREEK GENERATING STATION DOCKET NO. 50-354 As identified in Supplement No. 5 to the Hope Creek Safety Evaluation Report and the recently issued Facility Operating License NPF-50 for Hope Creek Generating Station (HCGS),
the NRC has imposed a license condition related to environmental qualification.
Specifically, License Condition (9) in the Hope Creek SER requires that, "Before startup following the first refueling outage, the qualified life of the electrical equipment under purchase order M-48 shall be recalculated on the basis of the actual temperatures monitored at the equipment locations during the first cycle of operations, with adequate consideration of margin."
This license condition originated from the NRC audit of the HCGS Environmental Qualification Program during the week of July 15, 1985, at which time the staff expressed concern regarding using average temperature for aging calculations.
Following the NRC audit, Public Service Electric and Gas Company (PSE&G) committed to evaluate the effects on equipment qualified life if the maximum normal service temperature was used in the aging evaluation, in lieu of weighted average temperature.
The effect of using the maximum normal service temperature would be determined by calculation (Arrhenius evaluation), or, at PSE&G's option, room temperature monitors would be installed to verify the accuracy of previously determined average temperature values.
00l\\
t in 8606040216 860602 PDR ADOCK 05000354 E
Director of Nuclear 2
6-2-86 Reactor Regulation For all purchase orders except M-48, the effect on equipment qualified life utilizing maximum normal service temperature was evaluated (either by Arrhenius evaluation, or, the existing aging requirements were equal to or greater than the requirements for the device) without the installation of a temperature monitor.
Our initial assessment of purchase order M-48 (Primary Containment Instrument Gas Compressor and Control Assembly), which was qualified based on calculated average temperature, indicated that a temperature monitor would need to be installed to verify the accuracy of the previously determined average temperature basis.
This was presented to the NRC in a letter dated, January 7,
- 1986, (C.A. McNeill, PSE&G, to E. Adensam, NRC).
Subsequently, PSE&G has re-evaluated this issue and has determined the ability to incorporate the effect of using maximum normal service temperature for purchase order M-48 by analysis.
Calculation No. MO48-ARRH-001, Rev.
O, has been performed on the basis of calculated maximum temperature, and the qualified life of the components have been derived by Arrhenius Methodology.
The new qualified life values l
are being incorporated in the HCGS maintenance and surveillance program to reflect the revised replacement schedule for l
the components.
The effect of using maximum normal service temperature has now been completed for purchase order M-48, consistent with the approach taken on other orders which have been previously accepted by the NRC.
On this basis, PSE&G has satisfied the provisions of License Condition (9) and requests that the condition be removed at the time that the full-power j
license is issued for Hope Creek Generating Station.
The attached Addendum to the Environmental Qualification Summary Report, Revision 4, reflects this re-evaluation regarding electrical equipment under purchase order M-48.
These revised sheets should be inserted in place of the existing sheets within the HCGS EQ Summary Report, Revision 4.
Sincerely,
$llt RN Attachment
Director of Nuclear 3
6-2-86 Reactor Regulation C
D. II. Wagner USNRC Licensing Project Manager R.W.
Borchardt USNRC Senior Resident Inspector II. Garg USNRC EQ Branch
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ENVIRONMENTAL QUALIFICATION
SUMMARY
REPORT ADDENDUM NO. 2 TO REVISION 4 4
i i
j ITEM REASON i
- 1. Cover Sheet Added Report No. EOSR-001 4
2.
EESS #73, Rev. 4 Changed the qualified lives i
of the components on the i
basis of their continuous exposure to the maximum ambient temperature of 80 F.
Ref. D has been changed to reflect the related i
Arrhenius Caliculation.
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l ENVIRONMENTAL QUALIFICATION
SUMMARY
REPORT FOR HOPE CREEK GENERATING STATION PUBLIC SERVICE ELECTRIC & GAS REPORT NO. EQSR-001 REV DATE PREPARED
, REVIEWED APPROVED NA4 ]& 0l S AA d?A~,'
S 8/2/84 Nil f'M.]
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l Prepared By .L. M9 Date 7N#/M. V i Reviewcd By
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h hh Date f lo7s l UIMeter Wataanrts ammstr sqEET aft. ND: MD48-CWF-002 CVI GAS C0pFRE550R AND CONTROL son nors aem e m sesynas eartaageerr DOCIAerrnrios sertsegem EUlstesegrr gaat.Ir. opas DESOtleflet PAsufETEBS WBCIFIB QUREEIIB SegCIFIED( OunLirIED
- crt0D ITEsel past:sse m
orenartic 100 days 180 days E.Pg.4, B.Pg.815 Test None 80 days (Il svstus (KL) PRI. tieg 8 COAL INST. GAS. A. Pg.F-2 (2) Tm 10. Ts e. ("rl g33 I48 F B.Pe 8115 15 SEE SHEET ATTACHED ressang -3psig to E. Pg.46 Adequate 0 33 seeGeer (estG3 1.0 in H,0 B.Pg.314 GAS C0pFRE550R AIID CONTROLS sussre. iors-30 af n 100 8.Pg.814 Not twq'd (43 ptWelsractusest HUPGDITT (g) then 95 CVI FtOODRIC/ (51 stumEL so.100NL8-F rsent N/A N/A N/A N/A N/A Not req'd Is0RTHINGTOM 5 RnDENTIG8 2.8x10'R G Note fl A. Pg. Note #1' 1.43x10 I 6 1.1x10 R 8 Mote f2 F2 Note #2 Test RG SEE TTACHED gu yrs y Test and Not req'd Periodic Maintenance E.Fg.46 8.C.D Analysis (7) ACIlsenCY Etsc 80*P Note 93 and Replacement a) WettrIED N/A required Ref. B,C,D. b) ACTUnL 7f N/A N/A N/A N/A N/A Not req'd (S) EDC3 rigs REACTOR segue l BLDG. RM. 4412.4413 l (9) AA0WE FEDOD IEVEL 0008estsuffGs IErteggeCEs BUTES j vgs I pc I A. Spec 10855-M-048(Q) Rev.6 B. Farwell & Hendricks Report 20001, dh 4/2/85 i (le) s IssCmEJ.T 1tstTD (10655-H48(Q)-104-1) YES X IEF. B 1. ty eso [ C. FSH letter did.1/21/85 ,O RADS for compressor, see Ref.S.. Pg.F2 I O. @ B - ARRH-M Rew O 5 (113 suuvertJJess suoD. 1.71x10 RADS for electrical components, see Ref.B. Pg.F5 ves I pEr.8.C. E. DITS 10855-D7.5, Rev. 4
- 2. Beta Radiation qualiff ed by Bechtel Beta Quellfication Report for
- ~
F. CCM #20261608 dt. 3/28/84, describes that P.O. 10855-M-48(Q). the specified temp. 148'F includes 15'F
- 3. For Thermal Aging information see Pages 19.19A,13,B17,B18, j
y$ g margin. B19 of Ref. B. Por replacement information - See Ref.D. In Ref. D. the qualified lives of the components have been calculated on the basis of maximum ambient temperature of 80*P, -}}