IR 05000311/1979021
| ML18079A471 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/19/1979 |
| From: | Bettenhausen L, Caphton D, Paolina R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18079A469 | List: |
| References | |
| 50-311-79-21, NUDOCS 7906260499 | |
| Download: ML18079A471 (8) | |
Text
Report No. 50-311/79-21 Docket No. 50-311 U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I
License No. CPPR:53 Priority------
Category _ _....;B;;...;l ___ _
Licensee:
Public Service Electric and Gas Company 80 Park Place
- Newa rd, New Jersey 071 01
. Facility Name:
Salem Nuclear Generating Station, Unit 2 Inspection at:
Hanc6cks Bridge, New Jersey Inspection conducted:
March 16 and March 22-23, 1979 Inspectors: dk-~
.
- Approved by:*
- -. -
-~...
. -
. --*-- *--- *---*-- -- - '.
D. L. Caphton., Chief, N~port Branch
.~~NSJr.an~~ A-*. *
- o. L. Caphton, Chief, Nuclear Support Branch No. 1, RO&NS Branch Inspection Summary:
date signea Inspection on March 16 and March 22-23, 1979 (Report No. 50-311/79-21)
Areas Inspected: Routine, unannounced inspection by regional based inspectors of containment and radiation process monitors 2Rll, 2Rl2A, and 2Rl2B; startup test program including test procedure review and verification, plans for plant startup testing; plant tour' of containment and auxiliary buildin The.inspection involved 18 inspector-hours onsite by two NRC regional based* fospectors and 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> onsi:te by one NRC regional based superviso Results:
No items of noncompliance or deviations were identifie Region I Form 12
{Rev. April 77)
7 9 0626 OL-iCf~
- Cl
~-
DETAILS Persons Contacted Public Service Electric & Gas Company Mr. E. Barradale, Project Construction Manager Mr. L. Fry, Senior Performance Supervisor
- Mr. R. Griffith, Senior Staff Engineer, QA Mr. C. Johnson, Startup Engineer
- Mr. W. Kittle, Resident QA Engineer
- &*Mr. A. Meyer, Site QA Engineer
~Mr. H. Midura, Manager - Salem Generating Station
- Mr. J. Ni:cho 1 s '* : Reactor Engineer
Mr. E. Roscioli, Senior Reactor Staff Supervisor Mr. W. Schell, Engineer - Reactor Staff Mr. A. Sternberg, QA Department Training Staff
- Mr. J. Stillman, Station QA Engineer
- Mr. J. Zupko, Jr., Chief Engineer United Engineers & Constructors, In **Mr. W. Copeland, QC Supervisor
- Mr. E. Welsh, Assistant Superintendent, QA
- .-*denotes those present at the exit interview ori March 23, 197 **denotes those present at the exit interview on March J~~ 197.
Previous Inspection Item Update (Closed) Open Item (50-311/79-17-01):
Change 1 to Startup Proce-dure 60 refers test personnel to the boron concentration control method of Appendix B, Section* (Closed) Open Item (50-311/79-17-02):
Changes to Startup Proce-dures have. corrected the use of Unit 1 nomenclature in Unit 2 procedure (Closed) Open Item (50-311/79-17-03)~
Thi~ item addressed the inconsistent manner in which removal of test equipment or restora-tion to normal operations was covered in Startup Procedure Licensee representatives stated that the work order system described in Station Administrative Procedure 9 would be used to control instal-lation and removal of test equipmen The inspector reviewed use of work orders in similar situations and had no further questions on this subjec *
- 3~: :*startup Test Program Approval and Review of Startup Procedures The inspector verified by observation of the original approval records that, except for the 3 procedures noted below, all startup procedures identified in the NSSS Startup sequence, SUP 80.1, for Unit 2, have been reviewed and approved as set forth~,in.'.the*:Salem Startup Manual and FSA The three start-up procedures not verified are:
SUP 81:13, Radiation Monitoring and Shielding Evaluation, to be reviewed by Station Operations Review Committee (SORC) on/about March 29, 197 SUP 81.14, Effluent Monitoring Systems, to be reviewed by SORC on/about March 29, 197 SUP 81.15, Chemistry and Radiochem.iStry Tests, stated by licensee representatives to have beeri reviewed and approved March 22, 197 This is an unresolved item, pending inspector verification of SORC and Station Manager's approval of these three. procedures (311/79-21-01).
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Startup Test Organization and Administration The Electric Production Department has responsibility for and control of the startup test activities. The test engineers will be drawn from the staff of the Reactor Engineer, augmented by several startup engineer The Startup Engineer will provide administrative support and test coordinatio The NSSS Start-up Sequenc~ Procedure states that the plant will be operated in accordance with Station Operating Instructions, unless the specific test procedure states otherwise; specific procedures have the Test*Engineer request the operators to place the plant in the status required by the tes The master copy of the test procedure will be maintained by the Reactor Engineer until released for test. The Test Engineer is then responsible for.conducti.ng a briefing of all personnel involved in execution of the test. The Salem Startup Manual, Section 5.12.2 states the method for change to startup proce-dures; cautionary notes about the applicability of Technical Specifications and-:.their limits on procedure changes are found in the Startup Manual and in various procedure The NSSS Start-up Sequence procedure sets down the general criteria for results revi*ew and acceptance and the program to be fo 11 owed in event of significant delay in:-.the testing progra *
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The Deficiency Report/Corrective Action Request system described in Chapter 6 of the Salem Startup Manual will continue to be used to identify deficiencies and exceptions and to track corrective action Test and Measurement Equipment Special test equipment and plant calibrations are supplied by the Performance Depattmen These are done following Performance Department procedures as they are called for either by Startup Procedures or by work orders issued by other depart-ment The Performance Department procedures note calibration
- information and identity for each test instrument called for in thELprocedures review by the inspecto No items of noncompliance or deviations were identifie Instrumentation Cables and Termination - Work Activity The inspector reviewed work performance, partially.completed work*
and completed work, as appropriate, of select cables including terminations and associated devices which contribute:.directly to the electrical continuity of the circui't to ascertain whether the requirements of applicable procedures have been met in areas relating:ta*identification,:storage, handling, installation, routing, separation, surveillance, inspection, and termination Documents examined included:
(1)
Detail Construction Procedure Nos. 2205, 2207 (2)
Quality Control Instructions Nos. 13-2-E, Revision l; 13-3-E, Revision 0 (3)
Receiving Report Nos. 15, 954; 15, 622 (4) Surveillance Report Nos. E-10, 736; E-10, 984; E-10, 992 ;. E-11004;. E-11041
.(5}
Termination Verification Report No. E-10, 497 (6)
Drawing Nos. 242748, Revision 1, and 242749, Revision*=1
()
_____.,,
5 Cables selected for review:
(1) Cable Nos. 2Rl2AM5-AQ, 2Rl2AM6-AQ, 2RllAMl~AT, and 2RllAM8-AT (2)
Reel Nos. 5874, 5621, and 5513 No items of::noncompliance were identifie.
Instrumentation Cables and Terminations - Review of Quality Records The inspector reviewed pertinent work and quality records relativ to instrument cables associated with the containment process radi-ation monitor to ascertain whether the records meet established procedures and* whether the records reflect work accomplishment consistent with NRC requirements and SAR commitments in the areas of receipt i nspettion,: materi.a ls ::certification; Hnstal l ation*:,r:eoords, nondestructive testing and nonconformances/deviation record *
Documents examined included: Data Revi.ew - Installation record report No. EI-lA Receiving Report Nos. 15994, 5120, 15,991, and 17,541 Quality Control Surveillance Report Nos. E-11041, E-11030, and E-1099 Cable Pull record report Nos. E-10831 and E-10383 Cable Termination record report Nos. E-10979 and E-10988 Control Document Nos. QCP-17-1, QCP-13-3, QCP-15, QCP-13-6, FP-213, FP-219, FP-302, and the Cable Control Systems Manual with attachments and memorandums Nos. 24 and 3 No items of.noncompliance were identified.
- (j
Instrumentation Components/Systems - Review of Quality Records The* inspector reviewed pertinent work and quality records for instrument components associated with containment process radi-ation monitors 2Rll, 2Rl2A, and 2Rl2B located in the facilities south penetra~ton area-,.~-~~e.l[~tion 78'0.to.. as.certa*in:.whe.ther the records reflect work accomplishment consistent *with NRC require-ments and SAR commitments in the areas*.of Recei:pt Inspection, Material Certification, Storage, Handling, Identification, Instal-lation and Calibratio Documents examined included: Purchase Order No. E-206240 Purchase Specification No. 76-8137, Revision O Receiving Inspection Report Nos. 17, 57r and 17, 91 Data Review - Installation Report Nos. CR-134A-9 *and CR-134A-13 Storage Check Report for Requirement No. E-76582 Certificate of Compliance for equipment, dated March 2, 1979 Certificate of Compliance for reference check sources No. 237 I, H, J, G, F, and K<
The inspector noted that calibration data, seismic qualification and vendor test data was not available for revie The licensee had issued a change order AT64 issue'4 dated March 3, 1979, author-izing partial shipment by the vendor making i:t impossible for vendor to perform calibrations and other tests necessary for determining instrument sensitivity and operational characteristics. The licensee indicated the missing data would be obtained from tests to be per-formed on site by the vendor at a later dat This item is unresolved pending NRC review of this test data against purchase specificati.on requirements (311/79-21-02).
e T
(j Instrumentation Components/Systems - Work Activities The inspector reviewed work performance, partially :completed.work and completed work, as appropriate, of the installation of the containment process radiation monitors 2Rll, 2Rl2A, and 2Rl2B. to ascertain whether the requirements of applicable specifications, work procedures, testprocedures, and inspection procedures have been accomplished in the areas of location, identification, instal-lation, type, range, materials, protection/cleanliness, and inspection Applicable documents examined include: Purchase Specification No. 71-8137 Purchase Order No. E-206240 Control Division Field Procedure (CD~F) Nos. CD-Fl, CD-F2, CD~F3, CD-F9, CD-FlO, and CD-F2 Field Procedure:(FP) Nos. FP-403 and FP-404 Detail Construction Procedure (DCP) Nos. DCP-2501 and 2502 Quality Control Instruction (QC!) No. QCI-11-1 Drawing Nos. 240605, 240633, 233057, 240886, and 233061 The inspector noted that redundant sample lines, Nos. 2937 KA and 2938 KA, were installed in the same -tray support approximately 4 inches apart and sampling from the same area at elevation 150'0
,
inside the containmen With the exception of the outlet (exhaust)
lines at elevation 78
11
, no other sample lines were observed going to or from the radiation monito Paragraph 4 of licensee FSAR Sect{on 11.2.3.l (Process Radiation Monitoring System) states.:that "the containment or Plant Vent Radiation Monitors (Channel Rll, Rl2A, and Rl2B) have asse~blies common to a 11 channe 1s.
These a re described as fo 11 ows:
Item (a):
The following control assembly includes a pump unit and selector valves that provide a representative sample (or a 11 clean samp 1e 11 ) to the detector Item (f):
The flbw control panel in the control room...
permits remote operation of the control assembl By operating a selector switch.*. or a local sample may be monitore (J
8.*
With respect to item (a) above, data was not available to assure that the installed sample location, sample line,configuration, and operating cha.racteristics of the containment radiation moni-
.tors 2Rll, 2Rl2A, and 2Rl2B is adequate to provide representative sampling of the containment atmospher This item is unresolved pending NRC review of qualifying data (311/79-21-03).
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For item (f) above, the inspector was unable to determine how or where the local 11clean sample 11 would be obtaine This item is unresolved pending NRC review of licensee evaluation and corrective action (311/79-21-04).
- Plant Tour The inspector toured the auxiliary building and the containmen Removal of construction wiring and scaffolding and cleanup of debris were underway in the containment building. Licensee representatives stated that the auxiliary building would be cleaned up within the next wee *
No items of noncompliance or deviations were Hlenti'fie.
Unresolved Items Unresolved items are*:those items for which further information-iis required to determine whether they are acceptable or items of noncomplianc Unresolved items* are identified in Paragraphs 3, 6, and 7 of this repor.
Exit Interview Inspectors met with licensee representatives as denoted in Para-graph l of this report at the conclusion of the inspections on March 16 and March 23, 197 The inspectors summarized the scope and the findings of this inspection as they are detailed in this report.