IR 05000272/1980018
| ML18085A123 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/25/1980 |
| From: | Ebneter S, Finkel A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18085A122 | List: |
| References | |
| 50-272-80-18, NUDOCS 8010240574 | |
| Download: ML18085A123 (6) | |
Text
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U.S. ~UCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Report N /80~18 Docket No. _.;;..50=---=2:..:..7..::2.-----'-_
Region I License N DPR-70 Priority -"----------
Category __
_.:C~---
- Licensee: *
Pub 1 i c Service Electric and Gas Company 80 Park Place Newark~ New Jersey 07101 Facility Name:
Salem Generating Station, Unit 1 Inspection at:
Newark, New Jersey Inspection conducted:
July 16-18, 1980 Inspectors:* {?,£,cf~U A. E. Finkel, Reactor Inspector n~~
.
Approved by:..)*,AV,
!.
- S. D. Eb~:fiief, Engineering Section No. 2, RC&ES Branch Inspection Summary:
Support date signed date signed
.R(~o.
date signed Inspection on July 16-18, 1980 {Report No. 50-272/80-18)
Areas Inspected:
Routine, announced inspection of qualification data for the electrical equipment inside containment associated with the Electrical System,
- Accumulator System, and the Steam Generator System as defined in the licensee's response to IE Bulletin 79-0lB dated April 18, 198 The inspection involved 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> at the licensee's corporate offices in Newark, New Jerse Results:
No items of noncompliance were identifie Region I Form 12 (Rev. April 77)
8010240
- DETAILS Persons Contacted Public Service Electric and Gas Company
- Mr. J. Gagliardi, Senior Engineer, Controls Division
- Mr: A. Gilrain, Senior Engineer, Electrical Division Mr. H. Heller, Manager, Nuclear Operations Mr. P. Moeller, Licensing Engineer, Production
- Mr. M. Rosenzweig, Senior Staff Engineer Quality Assurance Mr. J. Schubel, Senior Engineer, Controls Division
- Mr. R. Skarek, Licensing
- Mr. J. Wroblewski, Controls Division
- Mr. Y. Yaworsky, Assistant Chief, Controls Engineer
- Mr. C. Zimmerman, Production
- Denotes those present at the exit tntervie IE Bulletin 79-0lB Qualification Data Verification The inspector, on July 16-18, 1980, performed a verification inspection of the qualification documentation of the components of the following system The inspection was performed in accordance with the inspection instructions entitled 11 Inspection Requirements for Verifying Reactor Licensee Responses to IE Bulletin No. 79-018 11 *
Electrical System Accumulator System Steam Generator System Electrical System The inspector reviewed the qualification documentation for cables of the Electrical Syste Electrical Cables The electrical cables associated with this system and used in containment for the Accumulator System are~as'f~i1ows: (1) American.Insulated Wire Corporation (AIW)
The AIW cables.. -
. were qualified by Franklin Institute Research Laboratory (FIRL) and documented in Report No. F-C5115, dated April 197 The title of the report is 11Qualification Test of Electrical Cables in a Simulat~d Loss of Coolant Accident (LOCA) Environment".
The inspector reviewed the FIRL Report No. F-C5115 and.determined that the test results were within the environmental profiles that the licensee listed in their IE Bulletin 79-0lB response dated June 4, 198 (2) Boston Insulated Wire and Cable Company (BIW)
The inspector reviewed the BIW qualification test report erititled
"Flame and Radiation Cables for Nuclear Power Plants
, dated May 197 (Report No. B910)
A review of the data in BIW Report B910 indicated an apparent conflict with data listed in FIRL Reference Report No. F-C3859-BIW has corrected the wording of the report and the inspector determined that the test results of BIW Report 8910 were within the environmental profiles that the licensee listed in its IE Bulletin 79-0lB response dated June 4, 198 Accumulator System The Accumulator System which included the electrical cables discussed in
- item 3 above, also included electrical penetrations, isolation valves, instrument panels, and terminal block Conax Canister Type Assemblies - Electrical Penetrations The inspector reviewed the qualification report for Salem Unit.. 1,.
_,
entitled 11Design Qualification Report for Electrical Penetration Assemblies for Salem Nuclear Generating Stations", Conax W/0 7-80100, dated March 21, 1980, and Conax No. IPS-422, Revision A, dated May 8, 198 The report data were within the licensee's profiles for the Unit 1 sit Solenoid Valves - ASCO NP8316 and 8344 Series The inspector reviewed the Automatic Switch Company Test Report QAS21678/TR, dated March 1978, and Wyle Laboratory Report No. 44439-1, dated March 23, 197 The data in the above reports are within the profiles that this licensee has listed in their June 4, 1980 submitta Instrument Panel Enclosures The Wyle Laboratory report entitled 11Accident (LOCA) Test and Analysis of Five (5) Equipment Enclosure Types for Public Service Electric and Gas Company (PSE&G)
11 dated August 15, 1979, Revision A addresses the qualification of equipment enclosures for use inside reactor containment at Salem 1 and The following lists, the'equfpinent that was teste PSE&G P-SE&G
~
Panel N Drawing N Dimensions 2-Bay Vertical 234 205687-A-8863 21x5 1x7 1 1-Bay Vertical 237 205691-A-8939 21x2.5 1x7 1
'3-Bay Vertical 241 233063-A-1399 21xl0 1x5 1 4-Bay Vertical 335 211698-A-8863 21xl0 1x7 1 Wall-Mounted 444 233609-B-9611
11x31 11xl6
The test program was performed to verify the structural and thermal integrity of the equipment enclosures to withstand 'the pressure and temperature conditions that occur during a postulated Design Basis Accident (OBA).
An analytical approach was taken to assess and
- identify the maximum stress and thermal effects on each equipment enclosur The equipment enclosures were analyzed from three different points of vie The three analyses are Structural Analysis, Fluid Flow Analysis, and Thermal Analysi A brief summary of the Structural and Thermal Analyses approaches is contained in the following paragraph It was determined from the Structural Analysis that the conditions existing during a OBA event resulted in stress levels in panels similar to Panel 237 (Vertical Enclosure) were 200 times the maximum allowable level In order to mai.ntain structural in"tegrity of the enclosures, it was determined analytically that the differential pressure GAP) between the in~ide and outside of the enclosu~es must be limited to 0.5 psJg for panels similar to Panel 444 (Type 12 NEMA Enclosure) and 0.25 psig for panels similar to Panel 237 (Vertical Enclosure) during the OBA event as indicated by the stress levels in the following table I MAXIMUM STRESS IN 2' x 2.5' x 7' CONTROL P.r.NEL
.,
I
..
DUE TOAP = 0.25 psig MAXIMUM. STRESS ELEMENT APPROXI!-IATE
! ELEMENT :.oc.ATION
j 10 ga Plate Exterior I Internal Frame
\\ Door (10 ga)
! Door Latch Pin
{psi)
475 4, 735 4,059 21, 554 NUMBER STRESS ~TIO
0.03 45.2 109 !-iAXIMUM STRESS IN 38" x 31" x 161'
NE.i.'1.~ ENCLOSURE DUE TO ~p = 0. 5 psig MAXI.MUM STRESS
'ELEME!-iT APPROXL'1ATE ELEMENT LCCATION ( si)
NU?-'..BER STRESS RATIO I 12 ga Plate Exterior.
4,036 21 Door (12 ga)
.
4,927 121 ! Internal Stiffener 18,308 144 The data acquired during the OBA Tests were submitted to the respective Analyses Section for confirmation of their mathematical model.*
The Thermal Analysis was performed using mathematical models to predict the.component temperatures inside the equipment enclosures during a OBA event. The models were verified by actual tests to simulated OBA condition The testing and modeling have indicated that the thermal environment inside a vented equipment-enclosure is not as severe as the environment outside the enclosure in the early staqes of a OB t ~
. -- -- :
I c
.... -
The data obtained during the accident (OBA) test on Panel Numbers 237 and 444 show that the internal temperature of Panel No. 237 was higher for the first 26 minutes of the temperature/pressure/time
~refile. This indicates that Panel No. 237 (large enclosure) represents the "worst case 11 for thermal loading on equipment installed in this panel. After 26 minutes of test, the.two cabinets' internal temperature equalized and the thermal condition of the equipment inside the two panels was equalize The inspector reviewed the above documentation and determined that the results of the analyses and test data were within the environmental profiles that the licensee listed in its IE Bulletin 79-0lB respons dated June 4, 198 Terminal Blocks.~ Buchanan Model 616508-6 and 2B112N*
The B~chanan terminal blocks, Model 616508-6 and 28112N, were listed as qualified by Co.nax Corporation in a report entitled 11Qualification of Electrical Connection Terminal Blocks/Junction Boxes in Containment Environment in a Loss of toolant Accident or a Steam Line Break Accident for Public Service Electric and Gas Company for Salem Generating Station, 11 Report No. IPS-400, dated April 25, 197 The inspector reviewed the above report and determined that the results of the tests were within the environmental profiles that the licensee listed in its IE Bulletin 79-018 response dated June 4, 198 *. Steam Generator System The inspector reviewed the following qualification documentation for the listed transmitters in the Steam Generator Syste ~
Model 1153AHA Model 764 (Lot 2)
Model 763 (Lot 2)
Manufacturer Rosemount Barton }
Barton Qualification Report N Rosemount No. 3788 dated March 23, 1978 Barton Report dated December 20, 1979 The inspector determined that the results of the tests were within the environmental profiles that the licensee listed in its IE Bulletin 79-018 response dated June 4, 198.
Safety Evaluation Report (SER) Input The acceptability of qualification documentation identified in this report wi 11 be documented in the Safety Evaluation Report (SER) that is to be written for Sa 1 em The SER is p 1 anned to be issued by February 198 ~
Exit Interview At the conclusion of the inspection on July 18, 1980, a meeting was held at the Newark, New Jersey corporate office with representatives of the license Attendees at this meeting included personnel whose names are indicated by the notation (*) in paragraph The inspector summarized the results of the inspection as described in this report.