IR 05000272/1987034
| ML18093A585 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/23/1987 |
| From: | Murphy K, Vankessel H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18093A584 | List: |
| References | |
| 50-272-87-34, NUDOCS 8801200212 | |
| Download: ML18093A585 (7) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report N /87-34 Docket N License N DPR-70
Licensee:
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Facility Name:
Salem Generating Station, Unit 1 Inspection At:
Hancocks Bridge, New Jersey Inspection Conducted:
November Inspectors: *
12-7-5-21 date
.* Approved by:
1z_-2r--r-Test Section, date
Inspection Summary:
Inspection on November 16-20, 1987 (Inspection Number 50-272/87-34)
Areas Inspected:
Routine, Unannounced Inspection of the Post Modification Test Program, presently in progress during the refueling outage, including the review of test procedures for post modification tests, the witnessing of selected post modification tests, and the reviews of surveillance reports by PSE&G 1 s QA on post mod. tests. "The inspector also reviewed the status of the post mod. tests for the Charging Pump pulsation dampener Results:
No violations were identifie ~866~72 PDR ADOCK PDR G
- Persons Contacted Public Service Electric and Gas Company R. L. Baumert, Senior Staff Engineer T. Bialy, Electrical Enginer L. Chraska, Westinghou~e Representative (AMSAC)
M. Danak, Senior Enigneer
- R. Dulce, Principal Engineer, QA L. G. Hajos, Lead Engineer K. C. King, Engineer C. P. Lashkari, Senior Engineer G. A. Raggio, Station Licensing Engineer J. K. Sawhney, Senior Staff Engineer W. Strubmuller, Project Manager Special Proje~ts A. VanderWoude, Senior Staff Engineer
- J. W. Zupko, Jr., General Manager Salem Operations U. S. Nuclear Regulatory Commission
- K. H. Halvey Gibson, Besident Inspector, Salem
- T. J. Kenny, Senior Re;,sident Inspector, Salem 1&2
- Present in Exit Meeting held on Nove~b~r 20, 198.
Licensee Action on Previ-:ous Inspection Findings (Closed) Unresolved Item (272/87-27-01),
11Torgue Switch Settings for new Jamesburg Valves 11 The use of 11as found values" for the torque switch settings of the new Jamesburg butterfly valves of modification package 2202 had been questioned by the inspector in the previous inspectio Further inquiries into this matter revealed, however, that the required information for these settings had been found inside the limitorque housing, stamped on the cove This vendor information had been used for the torque switch setting This unresolved item is hereby close (Closed) Unresolved Item (272/87-27-02),
11Generation of system test procedures for certain modification packages 11 System Test procedures were not completed for certain modification packages (3) during the previous inspection period (272/87-27).
It was judged by the responsible modification engineers -that these particular modifications should have a system test procedure (ST) or, possibly, a revised surveillance procedure, to verify that the modified system will operate satisfactorily in an integrated manner with the other associated plant system Detailed system test procedures (STs) were produced by the respective subcontractors for packages IEC-2173 (Westinghouse) and 2232 (Combustion Engineering).
-2-However, for IEC-1890 that basically involves changes to system components, it was considered adequate to perform a surveillance test to verify that the new components perform satisfactorily within the syste To this end, the existing surveillance test procedure will be revised to reflect the new design situatio The inspector had no further questions on this unresolved ite For further details on the review of the new test procedures see Section 3 of this repor.
Post Modification Test Program 3.1 Test Procedure Review The procedures listed in Attachment A were reviewed for the following attributes:
Management review and approval
Procedure format
Clarity of stated objectives
Prerequisites
Environmental conditions
Acceptance Criteria and their sources
Attainment of test objectives
Degree of detail for test instructions
Restoration of system to normal after testing
Identification of*t~st personnel
Evaluation of test data
Quality assurance and Quality control involvement The two system test (ST) procedures reviewed for the above attributes were found to be adequat.2 Test Witnessing Scope All of the steps of Procedure ITTC/NC(87)-789, "Site Acceptance Test Procedure, Salem 1 and 2 AMSAC (ATWS Mitigation System Actuation Circuitry)" and for the functional test of the new W differential relays performed under W document 5D2 for SA-1 Relays were witnessed by the inspecto Test witnessing by the inspector included observation of:
Test personnel performance
Use of latest revised and approved procedure by test personnel
Designation of one person in charge of conducting the tests
Availability of sufficient test personnel to perform the tests
Coverage of test prerequisites
Use of acceptance criteria to evaluate test results
Verification that plant supporting systems are in service
In-service status of calibrated special test equipment required by the test procedure
._! **
-3-
Adherence to the test requirements of the test procedure during the tests
Timely and correct action by test personnel during the performance of the test
Data collection for final analysis by test personnel The inspector independently verified readings of system parameters during the test No violations were identified by the inspecto A PSE&G QA representative was present during the AMSAC acceptance tes He acknowledged the validity of the test results by stamping and signing the test document after completion of the tes.
Independent Inspection Efforts The inspector obtaines an update on the status of the pulsation dampeners for the Charging Pump* (Positive Displacement) of Salem-A dampener also was installed on the suction side of the pum The installation is now c"omp 1 et The vi bratj on test to verify the proper performance of the dampeners will be per~Drmed after obtaining mode 3 on the plan This test requirement was not incorporated in the test specification of modi fi cation package IEC-206 It wi 11 be performed, how*e.v~r, by. another group as-was done in the. case of Salem-2., In view of the identical piping design of Salem-I, it t~ expected that the test results will be close to those of Salem-The test results will be forwarded to the inspector via the NRC resident's offic.
QA/QC Interface The participation of the PSE&G QA Surveillance group in the post modification test program was evaluated by the inspecto A number of surveillance reports, pertaining to post modification tests performed during this refueling outage, as listed in Attachment B were reviewe It was noted by the inspector that checklists were not routinely used by the QA Engineers to check, amongst other items, adherence to administrative requirements during the testin As far as the inspector could determine there is no specific requirement in the QA manual for the use of the check lists during the surveilianc The inspector determined that checklists for test attributes and requirements do exit The surveillance reports reviewed by the inspector (See Attachment B)
reflects the absence of the checklist by their paucity of informatio Without the checklist, it is not possible to determine whether or not administrative and-other test requirements were met during the
-
performance of the test because these requirements are not listed as part of the surveillance repor The inspector informed PSE&G that routine use of these checklists during QA surveillance for post modification tests would significantly improve their existing audit progra The inspector had no further question.
Plant Tours Discussion The inspector made several tours of the plant including the control building, auxiliary building, service building, turbine building, safeguards building and reactor containment to observe the status of construction, work in progress, housekeeping, testing activities and cleanlines No unacceptable conditions were note.
Exit Interview At the conclusion of the site inspection, on November 20, 1987, an exit interview was conducted with the ~icensee 1 s senior site representatives (denoted in Section l)~
The findings were identified and previo~s
_inspection items were discusse At ~o tJme during this inspection was written material ~rovided to the*
licensee by the inspecto Based on. the NRC Region I review of this report and discussions held with licensee representatives during this inspection, it was determined that this report does not contain information subject to 10 CFR 2.790 restriction *
DCP N IEC-2173 IEC-2173 IEC-2173 IEC-2173 IEC-2232 IEC-2232 Attachment A Review of Post Modification Test Procedures Proc. N M13-PTP-103 Forms 103-1, 2, 3, 4 and 5 NS ID-EIS 87-33* W*
'-'
Rev. 0 M13-STP-002 Rev 0 ITTC/NC(87)
-789, Rev _0 M13-PTP-10 Forms 103-1, 2, -*~
3 and 4;. 502-1; 2-3 5587-ICE-35303, Rev O; (CE)
Title Installation of AMSAC ATWS Mitigation System Actuation Circuitry AMSAC Startup Test Procedure for Salem Unit 1 AMSAC Site Acceptance Test Procedure Approval Date 9/28/87 10/15/87 11/02/87
- Site Acceptance Test Procedures 10/31/87 Salem 1 and 2 AMSAC Installation of Bottom Entr /29/87 Incore Instrumentation Acceptance Test Procedure 07/22/87 for the Core Exit Thermocouple Processing System for Salem 1 & 2
- Attachment B QA Survei 11 ance Reports Report N I EC-N Area of Activity Date Performed 87-0924 2173 AMSAC; Reactor Protection 10/27/87 W Proc. NSID-EIS-87-33 87-0972 2173 AMSAC Computer 10/28/87 W Proc. NSID-EIS-87-33 87-0999 2173 AMSAC Computer 10/29/87 W Proc. NSID-EIS-87-33 87-1173 2173 AMSAC Acceptance Test 11/08/87 87-1239 1890 Modify T Hot + T Cold Indicators 11/10/87 87-1273 1890 Modify T Hot + T Cold Indicators 11/12/87