IR 05000272/1980010
| ML18082A813 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/21/1980 |
| From: | Caphton D, Rekito W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18082A810 | List: |
| References | |
| 50-272-80-10, NUDOCS 8007310131 | |
| Download: ML18082A813 (8) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Report N /80~10 Docket N ~272
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Region I Li cens.e _No. __ DPR-70 Priority ----------
Category ______ c ____ _
Licensee:
Public Service Electric and Gas C Park.Place N~wark, New Jersey 07101 Facilfty Name:
Salem Nuclear Generating Station Unit 1 Inspection at:
Hancocks *Bridge, New Jersey Inspection conducted:
April 22-25, 1980 Inspectors: ~~<12£#.R.*..
- . eki to' eactOrlnspector Approved by:
Inspection Summary:
Inspection on April 22-25, 1980 (Report No. 50-272/80*10)
~/:lo!f'o I date signed date signed
- . 'date signed date signed
. ~#1/oz>
Areas Inspected,: Routine, unannounced inspection of Containment Leak Rate Testing; inservice testing of pumps; surveillance of pipe supports and restraints; and licensee acti-0n on ~~evibus inspection finding The inspection involved 32 inspector-hours on site by one regional based inspecto Results:
Of the four areas *inspected, no items of noncompliance were found in three areas; one item of noncompliance was found in one area (deficiency Failure to meet CLRT reporting requirements, Paragraph 5.c).
Region I Form 12 (Rev. April 77)
8007 3 10/~/
- DETAILS Persons Contacted The below listed technical and supervisory personnel were contacte Public Service Electric and Gas Company
- B. H1cks, PSE&G Research & Testing Lab
- J. McAdams, PSE&G Research & Testing Lab
- M. Metcalf, PSE&G Resident QA Group
- H. Midura, Manager Salem Generating Station R. Newman, Operations Engineer
- J. Stillman, Station QA Engineer
- F. Twogood, Westinghouse NSD/RE/SU
- J. Zupko, Chief Engineer U.S. Nuclear Regulatory Commission
- W. Hill, NRC Resident Inspector L. Norrholm, NRC Resident Inspector
- Denotes those present at the *exit intervie The inspector also talked with and interviewed other licensee employees during the inspection including members of the QA staff and non-1 icensed operator.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (272/79-01-01):
Inservice testing of safety related pump The inspector verified that the applicable pump bearing thermocouples were calibrated as required by ASME Section XI, subsection IWP-321 Thi's item ;*s resolved.
- 3 Surveillance of Pipe Support and Restraints Documents Reviewed Salem Unit I Technical Spec.ification 3/4.7.9, Hydraulic Snubber Procedure MllB, R~v. 5. dated 9/26/79, Hydraulic Snubber Inspectio Steam Generator Snubber* Inspection Records dated 5/15/78 and 5/17/7 MSIV Snubber Inspection Records dated 3/24/8 Procedure M17B, Rev. 5, dated 10/2/79, Coded Component and
- Pipe Support Visual Examination (Class 1, 2, 3). Scope Long Term Inservice Examination Plan for Salem Nuclear Generating Station Unit The inspector reviewed the above documents to verify that visual inspections were conducted in conformance with procedural and TS requirement The inspector noted that no safety related hydraulic snubbers were found to be inoperable during the last visual inspection and that the licensee. is currently on an 18 month inspection interva *
No unacceptable conditions were found and. the inspector had no further questions in this are.
Inservice Testing of Pumps Documents Reviewed Procedure SP(O) 4.0.5-P, Rev. 4, dated 1/3/79, Inservice Testing of Pumps Unit I, Procedure M17D, Rev. 11, dated 4/18/80, Pump Surveillance Test Results Analysi Chilled Water Pump No. 11 & 12 test records dated 1/3/80, 1/21/80, 2/20/80, 3/20/80, 4/21/8 Containment Spray Pump No. 11 & 12 test records dated 1/21/80, 2/20/80, 3/20/80, 4/21/8 Safety Injection Pump No. 11 & 12 test records dated 1/21/80, 2/20/80, 3/20/80, 4/21/8 * * Scope The inspector reviewed the above documents to verify that required survei 11 ance tests were conducted at the required frequency and in conformance.with procedural and. TS requirement The inspector also reviewed the procedures for conformance with Subsection IWP of Section XI of ASME B&PV Cod No unacceptable conditions were found by the inspector during the document revie Test Witness On April 23, the inspector observed a plant equipment operator during the conduct of an inservice test of Component Cooling Pump No. 12. The. inspector verified that the test was conducted in accordance: with the approved procedure SP(O) 4.0.5-P and that the test resu.lts appeared satisfactor The inspector noted that the operator appeared.to be knowledgeable of the procedural requirements and. adequately trained in general but experienced a problem using the test instrument to measure pump bearing vibratio The operator recognized that the instrument readings appeared to be excessive and erratic so he questioned the ISI engineer and solicited a maintenance technician with a different vibration monttor who obtained satisfactory bearing vibration readings.
No unacceptable conditions were foun Test Instrument Training Following the test witnessed on April 23, the inspector interviewed three plant equipment operators who are assigned responsibility for using special test instruments (portable vibration monitors)
during. the, conduct of survei 11 ance operabi 1 i ty tests of safety relited pumps. Each of the operators reported that at various times they had experienced problems using the vibration monitor and had to rely on the ISI engineer or a maintenance technican to help in the use of the instrument in order to obtain the required dat The operators further explained that normally they were given instructions on the use of the instrument by their supervisor prior* to a test but never received more formal training relative to the operation of the instrumen Each of the operators expressed a lack of confidence in using the instrument because of their incomplete understanding and knowledge of its operatio *
The inspector identified the requirement of ANSI 18.1 to provide suitable training for non-licensed operators to prepare them for their assignment Tha inspector further discussed with the licensee 1 s representative his concern for the plant equipment: operators apparent lack of familiarization with the vibration monitor. The licensee's representative recognized this potential problem and committed to correcting the matter* by June l, 198 This matter will receive further review during a subsequent inspectio (272/80-10-01} (ontainment Leak Rate Testing Documents Reviewed Reactor Containment Integrated Leakage Rate Test Report -
First Retest - August 1979; Salem Unit I Technical Specification 3/4.6.l, Primary Containment.
. Procedure SP(O) 4.6.1.2, Rev. 0, dated 6/29/79, Containment System - Type A Integrated Leak Rate Test Unit Scope Salem Resident QA Audit Report 381, dated 8/14/79.
Procedure M16E, Rev. 13, Containment.Isoiation Type B & C tests and records of test results from the 1977 and 1979 refueling outage The inspector reviewed the above documents to verify that leak rate tests were conducted in conformance with procedural and TS requirements and that the results met the applicable acceptance criteria. The inspector also reviewed the technical summary report submitted to the NRC for accuracy and completeness as part of the reporting requirements of 10 CFR 50 Appendix Two unacceptable conditions were identified, and are discussed in paragraphs c and Reporting Requirements Appendix J to 10 CFR 50 requires that a licensee submit a technical summary report to the NRC approximately three months after the completton of each Type A periodic test. The report is required to contain a summary analysis of all Type B and C local leak rate tests performed since the last Type A test, including individual test results which failed to meet the applicable acceptance criterta and special tests performed as a result of replacing a component that is part of the primary reactor containment boundar *
Contrary to the requirements. identified above the inspector noted that the "Reactor Containment Integrated Leakage Rate Test Report" was sub-mitted to the NRC on March 31, 1980 which was approximately eight months after the Type A test completion on August 12, 197 In addition, the inspector identified several Type C local leak rate tests that were ~ot included in the report~ One was a special test conducted on valve ISS107 on May 11, 1978 resulting from valve replacemen Others included six val~es that failed their initial leak rate tests during the 1979 refueling outage and were the subject of LER 79~51/03L dated 8/ 10/7 Failure to meet the reporting requirements identified constitutes an item of noncompliance with 10 CFR 50 Appendix (Item 272/80-10-02) CILRT Acceptance The inspector reviewed the Type A test procedure and independently calculated the containment leak rate using raw data presented in the suminary repor The results are presented in Table The inspector's calculations essentially agree with the licensee's reported test results assuming no adjustment to the measured leak rate due to changes in the containment free volume duririg the test, as discussed belo The inspector identified the following two discrepancies with the Type A tes (1)
Discussions with the licensee's representative revealed that valve IVC-2 was not closed by its normal valve operator prior to the test as required by the procedure nor was it documented as such on the valve lineup shee However the valve was subsequently local leak rate tested and the results were conservatively added to the Type A test results in the summary repor {_2)
The reactor water level and containment sump level were recorded on data sheet The intended evaluation of this data for a possible effect (adjustment) on the measured leak rate of the test was not don Further review of the data by the inspector and licensee revealed that the data was not taken at the start and finish of the test which was essential for a valid evaluatio The licensee's representative retrieved other control room records and logs of pertinent plant parameters and system operations during the conduct of the test. This information satisfied the inspector that no additional water was added to the reactor coolant system during the test. The licensee proposed to correct these two discrepancies by (1) revising the procedure; (2) doing a detailed review of the plant conditions during the test for any possible in-leakage of water; (3) performing the necessary evaluation for possible additions to the test results; and (4) submitting a report as an addendum to the technical summary report by June 15, 198 Table 1 August 1979 - CILRT Conducted at Pa (47 PSIG) at Salem Nuclear Generating Station - Unit 1 Item Acceptance Criteria Reported Results Inspector's Findings Containment Leak Rate
.056
.059 (Mass Point) Upper 95% Confidence Level
,062
.062 on Leak Rate (Mass Point) Local Leak Rate Test
.000
.000 Additions (Type B & C) Containment Leak Rate at
.075
.062
.062 Upper 95% Confidence Level (.75 La)
Plus Required_Additions Supplemental Verification
.025
.020 Test Difference (.25 La)
Notes:
(1) All data reported in weight percent per da..
' The final acceptance of the 1979 CILRT results is unresolved pending NRC review of the licensee's further action (Unresolved Item N /80-10-03) Uriresolved Items Items about* whi.ch more information* is required to determine acceptability are* cons.idered unresolve Paragraph 5 of this report contains an unresolved tte * Exit Interview The. inspector met with licensee representatives (denoted in Paragraph 1) at. the conclusion of the inspection on April 25, 198 The inspector summarized the scope and findings of the inspection at that time.