IR 05000311/1978039
| ML18078A572 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/06/1978 |
| From: | Durr J, Mcgaughy R, Toth A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18078A571 | List: |
| References | |
| 50-311-78-39, NUDOCS 7901020109 | |
| Download: ML18078A572 (11) | |
Text
Report N Docket N U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT 50-311/78-39 50-311 Region I License N CPPR-53 Priority -------
Category __
B ____ _
Licensee:
Public Service Electric and Gas Company 80 Park Place Newark, New Jersey 07101 Facility Name:
Salem Nuclear Generating Station, Unit 2 Inspection at: Hancocks Bridge, New Jersey nspec or Inspector Approved by:
Inspection Summary:
1978 /I;;. //7.?
aate signed 1/~hz
/dat-signed I 1./2 )1;;
1date signed
/ffll1!l1,j; jtJ 'ff r
, date" sign Inspection on October 10-13 and 18-19, 1978 (Report No. 50-311/78-39)
Areas Inspected:
Routine, unannounced inspection by three regional based inspectors of Work Activities for installed devices to protect against degradation of membranes in primary water and waste monitor tanks, preparations for installa-tion of process radiation monitoring devices; and Quality Ver.ification Records for licensee followup activities relative to items reported to NRC under 10 CFR 50.55(e), containment personnel access hatch leak tests, primary coolant system accumulators procurement, steam generator and pressurizer level transmitter procurement, cable tray and conduit hardware procuremen The inspector also performed a plant tour-inspection, reviewed licensee action on previous inspection findings, and performed followup action as necessary to resolve questions which during the course of inspection of the above area The inspection involved ector-hours onsite by three NRC regional office based inspector :
No items of noncompliance were identifie Region I Form 12 (Rev. April 77)
7 9 0 1 0 2 0 10'\\
DETAILS Persons Contacted Public Service Electric and Gas Company
- S. Chawaga, Site QC Division Head
- J. Destefano, Site QA Engineer
- R. T. Griffith, Site QA Engineer R. Kirk, Senior Engineer
- H. S. Lowe, Site QA Engineer -
- D. L. Mclaughlin, Senior Construction Engineer
- A. Meyer, Site QA Engineer
- E. H. Meyer, Site QA Divison Head R. T. Stanley, Lead Mechanical Engineer W. 0. Straubmuller, Assistant Chief Designer, Mechanical
- P. E. String, Jr., QA/QC Coordi~ator United Engineers and Constructors, In *D. N. Blatman, Project QA Engineer R. Jorgensen, QC Records Supervisor K. Mills, QC Engineer - Records
- R. J. Phelps, Superintendent Field Quality Control R. C. Robinson, QC Assistant Mechanical Supervisor S. Shidner, QC Engineer - Records
- D. C. Snyder, Project Engineer
- E. A. Walsh, Assistant Superintendent Field Quality Control Westinghouse Electric Corporation N. Skorich, Site Mechanical Engineer D. K. Strong, Jr., Process/Nuclear Controls Engineer The inspectors also interviewed other licensee employees during the course of the inspectio They included Quality Control and con-struction craft personne *
- denotes those present at the exit interviews '.~ Pl ant Tour The inspectors observed work activities in-progress, completed work,*
and plant status in several areas of the plant during general inspection
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of the plant. The inspectors examined work items for any obvious defects or noncompliance with regulatory requirements or license condition Particular note was taken of presence of quality control inspectors and quality control evidence such as inspection records, material identification, nonconforming material identifi-cation, and equipment calibration tags. The inspectors interviewed craft personnel, supervision, and quality inspection personnel as such personnel were available in the work areas. Where more detailed inspection of an area was conducted, the inspection scope and findings are described in other paragraphs of the repor No items of noncompliance were identifie Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (311/78-19-01): Mechanical snubber bolt torquing_ and safety wirin The inspector examined procedures and records which included definitive and approved instructions for torquing snubber transition tube plate bolts and installing safety wirin The records included an engineering change notice and defic-iency reports which call for torquing of all snubber bo_lts and installation of safety wiring, deforming threads, or tack-welding bolt head Appropriate criteria are included in accordance with vendor recommendation The following specific documents were examined:
Procedure DCP-2403, Revision 4 (Paragraph 4.4)
Change Notice ECN-27957 Drawing PSBP-175152/1801503-01 Deficiency Reports DR-6672, 6728, 6875-6878 The criteria and work completion controls established by the above documents are sufficient to resolve this item. *
(Closed) Unresolved Item(311/78-19-02): Mechanical snubber hot/cold setting The inspector interviewed personnel and examined procedures and records relative to criteria for pin-to-pin spacing for mechanical snubber The applicable procedure (DCP-2403) has been revised to define that+ 2 inch tolerance is permissible for overall pin-to-pin installed spacin (The pin-to-pin deviations discussed in IE Inspection Reports 311/78-19, Paragraph 7 and 311/78-26, Paragraph 6 did not exceed this limit.) A+ 1/8 11 tolerance is defined for the movable portion of the snubber uni The snubbers for Main Steam Isolation valves have been checked by the licensee and comply with this criteria and applicable drawing #238965-D4130- The inspector examined the following specific documents:
- PSE&G Site Audit Report Findings SQAD-804 UE&C Audit Finding Response PS-ME-09-78-26 UE&C Engineering Condition Report 1849C UE&C Engineering Change Notice 27943 Drawing #238965-04130-2 Sheet 3 UE&C Procedure DCP~2403 Revision 4 Field Engineering Memorandum #M-3956 The 11 cold 11 design dimensions, coupled with the above tolerances resolves the question of limiting snubber settings. The inspector had no further question (Open) Unresolved Item (311/78-26-02): Interface control for system/
equipment turnover for testin The inspector ascertained that the pin-to-pin snubber dimensions were acceptable, in conjunction with his review of licensee actions regarding item #311/78-19-02 (previous paragraph).
The licensee's review of the SET system is not yet complet (Closed) Unresolved Item (311/78-29-05): Spring hanger setting criteri The licensee revised procedure DCP-2403, Paragraph 5.5.3(2) to require that spring hanger loads shall be read at the spring coil side of the movable piston plate. This appears consistent with the practice at the s1t The inspector had no further question (Closed) Unresolved Item (311/78-14-02): Control air system separation requirement Of 35 Deficiency Reports (DR's) written involving control air separation problems, the inspector reviewed 24 of the engineering dispositions on the DR' The inspector examined the work for 10 of the 24 DR's and determined that the re-work was in accordance with the engineer1ng dispositio (Closed) Unresolved Item (311/78-06-03): Vital cable tray overfil The vital cable tray overfill was identified in licensee QA Audit
.
Report No. 78 The inspector reviewed the proposed engineering change to trays identified in report no. 78 The work for the proposed change is to be scheduled PY the licensee and will remain as an open item on the licensee's internal monthly repor When work is completed this item (Ref. No. 393)*will be.closed by the licensee's QA organizatio The control of this item appears commensurate with other licensee open items.
(Open) Noncompliance (31.1/78-26-01): Implementation of pipe welding design requirement The inspector examined records and interviewed responsible engineering personnel at the site on October 12, 1978 to ascertain. generic corrective actions in-progress relative to the socket welding noncompliance identified in IE Inspection Report 50-311/78-2 The inspector selected "typical end prep-sleeves 9, 10, 11 and 16 11 on drawing 218268-A~8903-12 as an item similar to Detail 17 on that drawin He examined the applicable weld history record for the 8
butt-weld on the containment exterior end of penetration #10, (Mark
- 2-RH-158, field weld #FW-2-RH-158-1), and associated vendor documents for fabrication of the pipe and its weld-end-preparation The inspector examined the following specific records:
Design Drawing 218268-A-8903-12 Isometric Drawing RH-2-3 Sheet 1 Detail Drawing 240295-D-4388-3 Sheet 25 Fabrication Drawings F-5791 (QC 10,002) Revision 1 F-6302 (QC 12,461) Revision 5 Weld Procedure EB 90.1 NU Weld End Preparation Detail (Kellog) SK-67 Revision 1 Weld History Record FW-2RH~158-l The design detail examined by the inspector appeared to have been translated into fabricatio~ control document The licensee repre-sentatives stated that it was their intent to select a sample of design details which have similarities to Detail 17, and audit the implementation of those details to assure proper implementatio The inspector stated that the results of that audit will be reviewed in conjunction with any other corrective actions described in the pending response to the previous item of noncomplianc The inspection reviewed the preliminary hydrostatic test program to be employed during the post-repair acceptance testing of the noncomplying socket weld He discussed the need for meeting construction code test pressures arid temperature criteria where applicable, and a safety evaluation of those systems where such testing is not feasibl (Open) Unresolved item (311/78-02-04): Nondestructive testing of the steam generator nozzle ring Further review of the foregoing item by the NRC established that the steam generator nozzle ring welds do require a liq~id penetrant test (PT) in accordanc~ with paragraph N-51 Concurrent with the review, the licensee performed a PT of the ring welds which disclosed 5 relevant indications (3 linear and 2 rounded).
Two of the linear indications have been removed by grindin The third linear and 2 rounded indications require additional wor It is anticipated that the final disposition of these indications will be performed after the hot functional testin *
- Licensee Followu Activities Relative to Items Re orted to NRC Under 10 CFR 50.55 e Automatic Transfer of 4KV Outside Feed The inspector examined documents relative to the licensee actions described in the June 2, 1976 PSE&G letter to NRC, as related to Unit (Similar and associated actions relative to Unit 1 were previously reviewed and are documented in IE Inspection Reports Nos. 50-272/76-24, 76-32 and 76-36.)
The inspector examined the Unit 2 Startup Procedure #SUP-29 dated June 22, 1977 Section 10.6; this provides testing to 11verify the control circuitry which pre-vents interruption of Safeguards Emergency Contra 1 s load sequencing during a blackout situation due to restoration of off-site power."
The inspector also interviewed responsible licensee personnel who stated that the control cabinets for both Unit l and Unit 2 were modified by the vendor at the same time, with changes described in the PSE&G June 2, 1976 letter. Based upon successful Unit 1 tests described in IE Inspection Report No. 50-272/76-36, and provision for similar startup testing for Unit 2, the inspector had no further questions regarding this matte Lube Oil and Jacket Heat Exchangers The inspector examined records of actions described in the licensee 1s May 5, 1975 letter to NRC regarding a slight leak through the heat exchanger cast aluminum/bronze head The records showed that the design working pressure of the heat exchangers is 150 psig, and the leakage occurred during the hydrostatic 300 psig test. Leakage rate was one drop in four hour Technical evaluations of the condition were performed by the diesel generator vendor (Alco), the licensee, and the architect-engineer*
(UE&C).
Joint audit (by Alco and PSE&G) were conducted at the shops of the heat exchanger manufacturer (BASCO Division - American Precision Industries).
On November 14, 1977, field pressure testing was performed, results evaluated, the condition reaffirmed for cooler No. 2C-EDG, and the condition determined to be acceptabl The inspector examined the following records relative to the above:
PSE&G Inspection Report #18.10-34 dated June 5, 1975 PSE&G Audit Response Lett~r #5MI-03/06 dated June 6, 1977
- BASCO Letter to ALCO #CS0-75-861 dated June 17, 1975 ALCO Letter to PSE&G #DE-35245 dated August 7, 1~75 PSE&G QA Memo (Orban/Deblasio) dated September )6, 1975 UE&C Field Pressure Test Report #116-H-l dated November 14, 1977 UE&C Def1ciency Report #5130 dated November 15, 1977 UE&C Detailed Test Procedure Approval Record dated December 5, 1977 The inspector had no further questions regarding this matte.
Containment Penetrations - Personnel Access Hatch - Records The inspector examined records relative to leak testing of the contain-ment personnel access hatch (airlock). The inspector evaluated the above items with regard to criteria delineated in the Salem Final Safety Analysis Report (FSAR) Sections 5.5 and 5.2.3 and Appendix D, including Codes and Standards commitments identified in the FSAR Section 5.2.8.2 and licensee/contractor specifications/procedures/
instructions numbered 68-7123 (w/Addendum 1 through 9).
The inspector considered the following aspects relative to the above:
test pressures and duration commensurate with containment design pressure and applicable ASME Code; review of test procedure by appropriate organizations and personnel; record of test result evaluation/
acceptance; records of repair and retest as requ1red; and retrievability of record The inspector examined the following quality-related records relative to the above evaluations:
Procedure (CB&I), AL (A through D), Revision l Record Drawing, SAB-lOlA Sheets l and 2 No items of noncompliance were identifie.
Primary Coolant System Accumulators - Records The inspector examined records relative to the primary coolant system accumulators designated as #21 through #24 (PNJ-SIATAT - #1 through #4).
The inspector evaluated these items with regard to criteria delineated in the Salem Final Safety Analysis Report (FSAR) Section 6 (Table 6.2.2)
and Appendix D, including Codes and Standards commitments identified in the FSAR Sectiori 6,* and licensee/contractor Purchase Order No. S46-F70616 *
The inspector considered the following aspects relative to the above:
seismic requirements, design temperature and pressure, receipt inspec-tion quality control documentatio The inspector examined the following documents relative to the above:
Westinghouse Purchase Order #546-F70616 w/Change Notice dated March 6, 1969
PSE&G Data Review - Receiving Report #MR-231-546 and #MR-231-545 UE&C QC Inspection Report (Shop) dated February 17, 1970 Qua 1 i ty Contra 1 Drawing Conformance Check Report dated May 18, 1970 Westinghouse Specifications #676441, #676452, #677019 Delta Southern Co. Drawings #41050, #41045, #41051 Westinghouse QC Release #1342 ASME Form U-lA for drawing #41051-70-1 Westinghouse letter #PSE-78-516 dated May 4, 1978 Findings: The inspector identified two items as unresolved, as discussed in sub-paragraphs a and b belo The purchase order #F70616 references specifications #676441 and
- 676452; however, the specification #676452 is applicable to another reactor facility. Specification #677019 is the commen-surate specification for the Salem facility, but it is not referenced in UE&C microfilm records, files, documents examined by the inspecto However, a copy was located at the UE&C records center on sit Sizing, painting, and lifting-lug requirements of specification
- 677019 did appear in a March 3, 1969 Change Notice to the pur-chanse order, although the reference to specification #676452 had not been change Receiving and inspection records indicated that the appropriate parameters of specification #677019 had been trans-mitted to the vendor, inspected and confirme The licensee stated that a purchase order change notice existed which clarified the applicable requirements, but that this was not at the site, nor required to be at the site. This item is unresolved pending review of the clarifying documen (311/78-39-01) The purchase specifications #676452 and #677019 identify accumu-lator operating conditions as 120° to 150oF, and design temperature as 300° The Salem FSAR Table 6.2.2 identifies operating tempera-tures of 50° to 150° The specifications do not require verifi-cation of fracture toughness of the accumulator materials; this is consistent with the applicable ASME Code (1966 Section III Class C) and the FSA However, Westinghouse letter #PSE-78-516 (regarding Unit l accumulators purchased under the same purcha~e order) indicates that current code rules and material manufacturer *
practices suggest that the accumulator minimum operating tempera-ture be limited to 70° by procedure The Salem Precautions, Limitations and Setpoints Document provided by Westinghouse reiterates the 70° requiremen The operating procedure #OI-I.3.4 (Revision 3) incorporates the requiremen The records examined by the inspector support the conclusion that the operation of the accumulators will be consistent with their functional capability. However, it 1s not clear that the 50°F lower limit allowed by FSAR Table 6.2.2 may be permitted for the procured accumulators. This item is unresolved pending licensee review of the basis for the SAR 50°Fspecificatio (311/78-39-02)
Steam Generator and Pressurizer Level Transmitters The inspector examined records and inspected the physical installation of differential pressure transmitters of the liquid level sensing systems for four steam generators and the pressurizer (three trans-mitters for each equipment piece). Barton model #764 (serial #173 through 175) transmitters had been installed in the Pressurizer Pro-tection Channel cabinets to replace three model #386 original device Replacement of the 12 transmitters for the steam generators 1s also planne The inspector interviewed licensee and NSSS contractor site personnel regarding environmental qualification test result questions associated with this particular model transmitter at another site. The licensee representative ad~ised the inspector by telephone on October 19, 1978 that this matter was under review by the PSE&G off-site engineering group, that an engineering change notice was imminent, and that the matter is currently under review by NRR in conjunction with the main steam line break analysis for Salem Unit 2, and general NRR requests to PSE&G for equipme~t environmental qualification dat The inspector examined the following documents relative to the above:
Westinghouse Equipment List, file Cl09303, dated January 30, 1974 Purchase Orders #El58838; #265750; #546-CIC-140889-BN Westinghouse QC Release #SQR-54166 dated April 5, 1972 Drawings PSBP-Cl09303 and Cll9617 and #117586 Data Receiving Report QC #17,109
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QC Surveillance Report #E8484 (QC #4547)
The inspector had no further questions at this tim The inspector identified no items of noncompliance.
- 10 Membranes In Primary Water Storage and Monitor Tanks The inspector examined measures implemented to assure against undetected degradation of membrane liners in primary water storage tanks and monitor tank He reviewed piping diagram #205330-A-8736-6 and observed physical installation of strainers and differential pressure sensor/transmitters across the strainers. This completed IE review of Unit 2 related actions proposed by the licensee, as discussed in IE Inspection Reports 50-272/73-02, 73-13, 74~09 and 76-07 (regarding Unit 1).
No items of noncompliance were identifie.
Cable Tray and Conduit Fittings The inspector examined the approved vendor list for field purchases and examined a typical purchase requisition for cable tray and conduit fitting The vendor (Unistrut), appeared on the list of approved vendor No other vendors were identified for this type materia No items of '.noncomp1iance were identifie.
Radiation Monitoring System - Auxiliary Building The inspector reviewed the location and installation requirements of the Auxiliary Building Radiation Monitoring System Equipmen The inspector reviewed the following drawings:
Location Drawing No. 244150-A-1642-2 Conduit Plans Drawing No. 242776B9675 Adaptor Brackets Drawing No. 242670D4485 Area Detectors Drawing No. 4309-2 (2R29)
Area Filter Detector Mounting Drawing No. 245120B9690 The inspector determined that the Class lE monitors for this system have not yet been received at the site. The radiation monitoring system work is only partially installed and cannot be completed until the various Class lE monitors are receive The inspector advised the licensee that documentation and installation of Auxiliary Building
.Radiation Monitoring System will be examined at a future inspectio..
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No items of noncompliance were identifie.' Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items*of non-compliance, or deviations. *Unresolved items disclosed during the inspection are discussed in paragraph..
1 Management Interviews The results of inspection activities conducted October 10-13, 1978 were presented at a site meeting on October 13, 197 Additional meetings were held October 19, 1978 to discuss the result of inspection activities on October 18-19, 1978 and October 19, 197 Attendees at the meetings included personnel whose names are indicated by notation (*) in paragraph The inspectors summarized the results of the inspection as described in this report.