IR 05000311/1988019

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Insp Rept 50-311/88-19 on 881003-07.No Violations Noted. Major Areas inspected:post-mod Test Program,Performed During Recent Refueling Outage,Review of post-mod Test Procedures & Test Results for Completed Tests.Unresolved Item Noted
ML18093B279
Person / Time
Site: Salem PSEG icon.png
Issue date: 10/31/1988
From: Eapen P, Van Kessel H
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML18093B278 List:
References
50-311-88-19, NUDOCS 8811080060
Download: ML18093B279 (10)


Text

Report N Docket N License N Licensee:

U.S. NUCLEAR REGULATORY COMMISSION

REGION I

50-311/88-19 50-311 DPR-75 Public Service Electric and Gas Company P.0. Box 236 Hancocks Bridge, New Jersey Facility Name:

Salem Generating Station, Unit 2 Inspection At:

Hancocks Bridge, NJ Inspection Conducted:

October 3-7, 1988

~bJ Inspector:

Engineer Henri F. van Kessel, Reactor Approved by:

}0-"3J-<jf8'

date 10/3, 1~v Bate Inspection Summary:

Inspection on October 3-7, 1988 (Report No. 50-311/88-19)

Areas Inspected:

Post Modification Test Program, performed during the recent refueling outage, including the review of post modification test procedures and test results for completed test The inspector also witnessed a con'tinuity check and a short circuit test for a multi conductor cabl The involvement of QA in the post modification test program was reviewed as wel Results:

No violations were identifie One unresolved item was identified in connection with the absence of restorati9n steps for temporary modifications in a special tes RR11080060 881102

~6R ADOCK 0500a~b1 G!

DETAILS Persons Contacted Public Service Electric and Gas Company R. Gibbs, QA Engineer

  • P. G. Galleshaw, Project Manager
  • M. Gray, Licensing Engineer
  • H. Gross, Sr. Engineer M. Marroui, System Engineerings Group Head
  • L. K. Miller, General Manager Salem Operations S. Leahman, Lead Instrumentation Engineer A~ Orticelli, Outage Manager J. Pick, Lead Test Engineer L. Piotti, Senior Staff QA Engineer L. Preihs, Senior Engineer G. Raggio, Station Licensing Engineer A. Sternberg, Training Coordinator D. Tauber, Station QC Supervisor R. Sarceni, Sr. Engineer U.S. Nuclear Regulatory Commission
  • R. W. Borchardt, Senior Resident Inspector
  • K. Halvey Gibson, Resident Inspector
  • Denotes those present at the exit interview on July 22, 198.

Post Modification Test (PMT) Program (72701)

The inspector selected the packages listed in Attachment A for review with respect to post modification testin The technical details and the existence of the safety evaluation were verified to be in accordance with 10 CFR 50.59(b).

The required post modification testing conducted for each selected modi-fication package was discussed with the licensee. These test procedures are identified in Attachment There are 3 different types of procedures involved:

(1)

Functional Test Procedures (System Specific)

(2) Special Test Procedures (STP) (System/Component Specific)

(3) Generic Test Procedures (Component Specific)

  • 3 PMT Procedure Review (72701)

All of the functional and specific test procedures as 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

References

Initial conditions

Attainment of test objectives

Test performance documentation and verification

Degree of detail for test instructions

Restoration of system to normal after testing

Identification of test personnel

Evaluation of test data

Independent verification of critical steps or parameters

Quality control and assurance involvement It was noted that none of the test procedures contained a signature/initial verification sheet to identify the signatures and initials of test and QA personnel involved in the tes A review of the pertinent administrative procedures revealed that there is no requirements for such a signature verification shee Also, there is no requirement for the independent verification, by QA, of restoration, steps to restore original system condition~ after the installation of temporary system changes such as lifted leads, electrical jumpers, and test instrument The test procedures are not approved individually by SOR However, they are reviewed by the Project Team Leader and the responsible system enginee SORC, however, does approve the overall modifica-tion package, including the test procedure Generally, the PMT procedures are not treated similar to the Preoperational Test (POT) procedures implemented prior to the licensing of the plan The Salem POT procedures for instance, were approved individually by POR.2 PMT Witnessing The inspector witnessed the short circuit test and the continuity check of multiple conductor cable ZAC668AT1 (push button module 2MD5884) which is a part of modification package 2EC-2151

'*

"Correction of Human Engineering Deficiencies.

These tests were conducted in accordance wjth Attachment V (of Procedure M13 STP-001),

11 Instrument Functional Checkout Action Sheet.

The test witnessing included observation of the following attributes:

Overall crew performance

Use of lates~ revised and approved procedure by test personnel

Designation of one person in charge of conducting the tests

Avail abi 1 i ty of suffi clent test personne 1 to perform the tests

Coverage of test prerequisites

Use of acceptance criteria to evaluate test results

Verification that plant supporting systems are 1n service

In-service status of calibrated special test equipment required by the test procedure

Adherence to the test requirements of the test procedure during *

the tests

Timely and correct action by test personnel during the performance of the tests

Data collection for final analysis by test personnel The tests were conducted successfull No negative observations were made by the inspector and no violations were identifie.3 Test Result Evaluation The test procedures listed in Attachment C were reviewed to verify that adequate testing was accomplished in order to satisfy regulatory requirements and licensee commitment The inspector also verified that uniform criteria were being applied for evaluating completed modification tests in order to assure their technical and administra-tive adequac The test results were reviewed for:

Test changes

Test exceptions

Test deficiencies

Acceptance criteria

Performance verification

Recording of conduct of test

  • QA inspection records

Syste~ restoration to normal

Independent verification of critical steps or parameters

Identification of test personnel

Verification that the test results have been approved With respect to PMT procedure M13 STP-001-2EC-2193, 11SSPS P-9/Turbine Reactor Trip Modification 11, it was noted that the temporary change of step 9.21 (for the installation of a Digital Volt Meter) is never restored in the procedur Also, the restoration of many temporary

  • changes is not accomplished because the test changes, introduced via Attachment 1, inadvertently, eliminated the restoration step An example is step 9.2, which lifts the NIS Leads of Rack 78-TB-123-1 and of Rack 79-TB223-These leads are restored in steps 9.36.1 and 2, but these steps have been deleted via Attachment The inspector identified no hardware problems resulting from the above inadvertent deletion of restoration requirement from the procedur The responsible test engineer was developing a response to this findin Unresolved Item No. 50-311/88-19-01 has been assigned to track the response to this findin The inspector reviewed the qualification records for all of the test engineers assigned to the nine modification packages identified in Appendix All of these test engineers met the requirements of ANSI N45.2.6, 11Qualifica-tion, and Testing Personnel for the Construction Phase of Nuclear Power Plants.

11 QA/QC Interface (357448)

A number of QA Surveillance Reports were reviewed to assess QA involvement in Post Modification Testing (PMT).

These QA Surveillance Reports are listed in Attachment They apply mostly to the modification packages listed in Attachment The selected reports indicate adequate involvement in the PMT program in the form of test witnessing by Q All findings were satisfactory. It was noted, however, that no check lists were used in any of the surveil-lances reviewe These check lists are available but were not used during this refueling outa.ge to record the attributes reviewed during the surveillanc.

Plant Tours The inspector made tours of the plant including the control building, control room, switch gear rooms, auxiliary building, turbine building, and the service water pump house to observe the status of work in progress, housekeeping, testing activities and cleanlines.

Unresolved Items Unresolved items are matters about which more information is required in order to determine whether they are acceptable, an item of noncompliance, or a deviation. A new unresolved item in this report is identified in para*graph 2. 3.

--*

........... *,

  • *

Exit Interview At the conclusion of the site inspection, on October 7, 1988, an exit interview was conducted with the licensee 1 s senior site representatives (denoted in Section 1).

The findings were identified and previous inspection items were discusse At no time during this inspection was written material provided 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 restrictions.

ATTACHMENT A Page 1 or 2 MODIFICATION PACKAGES ADDRESSED POST MODIFICATION TESTING DCP N DESCRIPTION TYPE OF TEST TEST PROC. N EC-2174 ATWS Mitigation System-Startup Test NSJD-EIS-88-31 Activation Circuitry-Site Acc. Test M13-STP-002-2EC-Actual Test-2174 2EC=2187 Demolition of BIT Tank-4 Hydro Tests M13-JVP-502 and BIT/BAT Recirc Lines-Functional Test M13-PTP-206 Heat Tracing-OPS Surv. Test SP(0)4.3.3.l(a)l 2EC-2203 Replace 7 Butterfly Valves-Maint. MOV M13-PTP-401, in SW Bays Procedure 202; M13-IVP-502 M3Q-1; M3L 2SC-2003 Add 2 11 Recirc. Line to AFW-Standing Water Test Section 9 of Pump No. 23-Hydro (1500psig)

2SC-2003-Flow Instr. Veri Vendor Inst (Controlotron)

2EC-2183 Add spacer Rings for Przr-Visual Inspection Safety Valves (2PR 3,4, during op. conditions and 5)

-QC hold points during installation 2EC-2193 Delete Rx Trip on Turbine-Channel Cali IC-16.1015, 16, Trip for < 50 % Rx Power-Functional SSPS 17' 18-Time Response 2IC-18.008, 9;

-Surveillance 2IC-18.4.002, 5-Funct. Site Ac SP(O) 4.3. AH.I, M13-STP-001-2EC-2193 AHK 2EC-1915A InCore Instr. Mod Pkg ( 1)

Run 5 Power Cables for Megger Cables the 2 backup display units, demultiplexer unit, ref-JBs Pkg (2)

Install new CET Processor see 20E2232 CE 1 s 5587-ICE-35303 in Control Room

DCP N EC-2232 Pkg (1)

Pkg (2)

Pkg (3)

2EC-2230 Pkg (1)

Pkg (2)

Pkg (3)

DESCRIPTION Bottom mounted InCore Instr. System (BMICI)

New Flux Thimbles T/Cs

  • Wear Inserts Demolition Rx Head TIC Co Install 4 Clamps on Spare Head Adaptors RTD Bypass Elimination Demolition RTD Bypass Install new RTDs and new electronics in Inst Racks Pull wiring from RTDs to RPS Cabmets TYPE OF TEST Validate SPDS and P250 inputs Hydro (10 Min.)

ISI pipecaps Hydro Fund Test Pro AMS Tune Response Test ATTACHMENT A Page 2 or 2 TEST PROC. N CE 1 s 5587-ICE-35303 DCR-2EC-2232 Same as for BMICI (for RCS)

CES 5587-ICE-35307

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ATTACHMENT 8 QA/QC SURVEILLANCE REPORTS Report N DCP N Area of Activity Date Performed 88-0733 2EC1915A InCore Instr. Mods 9-15-88 (Pkg 2)

Control Room Racks 88-0735 2EC2151 Human Eng. Deficiencies 9-14-88 Control Room Panels 88-0736 2EC2151 Human Eng. Deficiencies 9-14-88 Control Room Racks Tests 88-0737 2EC2230 RTD Bypass Elimination 9-14-88 Relay Panel 88-0866 2EC2174 AMSAC Tests 9-21-88 Control Room Racks 88-0871 2EC2187 BIT and BAT Recire, Mo Anchor Bolt Holes 88-0885 2EC2150 Push Button Mo Control Room 88-0890 2EC1915A InCore Instr. Mods 9-23-88 (pkg 2)

Meggar/Continuity Test 88-0891 2EC1915A InCore Instr. Mods 9-23-88 Termination Check

..

Proc. N M13-STP-003-2EC-2174 M13-STP-002-2EC2174 Ml3-STP-001-2EC2193 M13-IVP-502-2EC-2187 5587ICE35307-2EC-2230 ATTACHMENT C TEST RESULTS EVALUATION Description Rev. N AMSAR Startup - Test Procedures

AMSAC Site Acceptance Test Procedure

SSPS P-9/Turbine Reactor Trip Modification

Safety Injection, New Sample Flask 8 Piping

Hagan Rack Functional Test Procedure 2