IR 05000315/1978037

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IE Insp Repts 50-315/78-37 & 50-316/78-38 on 781218-20.No Noncompliance Noted.Major Areas Inspected:Calibr & Surveillance of safety-related Components,Implementation of ASME Code XI & Pump & Valve Test Program
ML17317A981
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 01/29/1979
From: Mcgregor L, Reyes L, Streeter J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML17317A980 List:
References
50-315-78-37, 50-316-78-38, NUDOCS 7903130062
Download: ML17317A981 (9)


Text

U.S.

NUCL AR REGULATORY COHHISSION OFFICE OF INSPECTION AND ENFORCEHENT

REGION III

Report No.:

50-315/78-37; 50-316/78-38 Docket No.:

50-315; 50-316 Licensen No.: DPR-58:

DPR-74 Licensee:

American Electric Power Serivce Corporation Indiana

& Hichigan Power Company 2 Broadway New York, NY 10004 Facility Name:

Donald C.

Cook Nuclear Power Plant, Units

6

Inspection At:

D. C.

Cook Site, Bridgman, HI

/~

Inspectors:

L, A. Reyes J

L. G. HcGregor

~

Approved By:

JP F. Streeter, Chief Nuclear Support Section

(Date)

1" c'j j'/

(Date)

'A~/~q (Date)

Ins ection Summar Ins ection on December 18-20 1978 (Re orts No. 50-315/78-37 50-~16/78-38)

Areas Ins ected:

Routine, unannounced inspection of calibration and surveillance of safety related components and equipment and implementation of ASHE Code Section XI and pump and valve test program.

The inspection involved 38 inspector-hours onsite by two NRC inspectors.

Results No items of noncompliance or deviations were identifie DETAILS Persons Contacted

>>D. Shaller, Plant Manager

  • B. Svenson, Assistant Plant Vanager
  • E. Smarrella, Technical Superintendent

>>E. Abshagen, Quality Assurance Auditor D. Duncan, Control and Instrumentation Supervisor T. Beilman, Quality Control Coordinator R. Bischoff, Instrument Engineer E. Kant, Performance Supervisor J. Rischling, Quality Control Coordinator R. Keith, Operations Supervisor R. Dudding, Maintenance Supervisor

  • Denotes those present at exit interview.

The inspector also contacted several other licensee employees, including members of the technical and engineering staffs, reactor operators and clerical personnel.

Previous Ins ection Findin s (Closed)

Noncompliance (Item 1 IE Report 50-315/78-24:

50-316/78-22)

Failure to declare the turbine driven auxiliary feedwater pump inoperable when the pump surveillance test results of June 7,

failure to take the action required by TS 3.7.1.2.

The inspector review-ed the revised surveillance test procedure and the test resu s

months of October and November 1978.

The licensee's corrective actions were acceptable.

(Closed)

Noncompliance (Item 2 IE Report 50-315/78-24; 50-316/78-22)

Failure to verify that the discharge pressure of the centrifugal

'harging pump was ~ 2405 psig while conducting the monthly surveillance test.

The inspector reviewed the revised surveillance test procedure 1 78.

The and the test results for the months of Ocotber and November

licensee's corrective actions were acceptable.

(Closed)

Noncompliance (Item 3 IE Report 50-315/78-24; 50-316/78-22)

Failure to include all information required by section XI on the in-se rvice test records and to declare pumps inoperable when the test results were in the required action range.

The inspector reviewed t e

the new procedure No.

12THP-4030.STP.022, Rev. 0, "ISI Pump Test Program",

which provides directives for instrument calibration requirements, allowable test ranges of test data, and assignments of responsibilitie r

'he inspector reviewed the test results of the CCW and ESN pumps for the months of October and November, 1978.

The licensee's corrective actions were acceptable.

3.

Pum and Valve Inservice Testin (Unit 1)

The inspector conducted a review of the planned implementation of the inservice testing of Class 1, 2, and 3 pumps and valves in accordance with Section XI of the ASHE Boiler and Pressure Vessel Code 1974 Edition and Addenda through Summer, 1975.

The inspector reviewed the below listed procedures to determine that the procedures to be used to implement the pump and valve inservice testing were reviewed and approved as required by the Technical Specifications; the procedures contained detailed stepwise instructions; the technical

'ontent of the procedures would result in a satisfactory testing as per Section XI of the ASME code:

a.

Essential Service Water System Water System Test Procedure No.

1-OHP-4030-STP

.020 Rev,0 b.

Component Cooling Water System Test Procedure No.

1-OHP-4030-STP

.020 Rev.

c.

Letdown and Charging System Operability Test Procedure No.l-OHP-4030-STP.004 Rev.

The above mentioned procedures included provisions for testing of valves and pumps in the respective system.

No records were available for review because the regular 40-month ISI interval and the implementation of Section XI for pumps and valves were not scheduled to start until late December, 1978.

No items of noncompliance or deviations were identified.

4.

Licensee Event Re orts on the Rod Position Indication S stem (Units 1&2)

The inspector discussed with the licensee the problems occurring in the Rod Position Indication (R?I) System that 'have caused a large number of LER's at both units.

The licensee appears to be actively seeking a

solution but an immediate solution does not appear to be forthcoming.

The licensee stated that Westinghouse is currently testing an upgraded hardware package to replace the existing conditioning modules and readout devices.

There is no schedule for the installation of the new system at this time.

No items of noncompliance or deviations were identifie.

Calibration of Safet Related Com~onente Re aired b

Technical S ecifications (Unit 2)

The inspector reviewed plant calibration records, selected logs and records for the below listed calibration activities.

This review was performed to determine that the frequency of calibration was met; the service status of the system was in conformance with the applicable limiting conditions of operations; the procedures used to calibrate the componenets were reviewed and approved as required by the Technical Specifications; the procedures used contained acceptable trip settings using applicable technical soecification requirements; the procedures used contained detailed stepwise instructions; the technical content of the procedures would result in satisfactory calibration; the quali-fications of two individuals in the I&C group having responsibilities for performing calibrations were adequate.

a.

Nuclear instrumentation intermediate range compensation Test IMP 049 (This test also includes the following tests IMP-020, 021, 061, 077, 091).

b.

Incore movable detector calibration, removal and replacement.

Test IHP-065 c.

Pressure indicating calibration Test IhP-087 d.

Delta "T"/Delta "T" average protection Set II Calibration Test IMP-095 e.

Pressurizer level transmitter calibration Test I."P-098 I

f.

Reactor coolant flow Set II Test I15P-100 g.

Steam generator level protection Set II Test IMP-105 h.

Pressurizer pressure protection Set II calibration Test IMP-116 i.

Lower containment pressure protection Set II calibration Test IHP-120 j.

Nuclear instrument calibration intermediate range (N35-N36)

Test IHP-130 K.

Nuclear instrument calibration power range (N41, 42, 43, 44)

Test IHP 131 l.

Rod control calibration Test IHP-131 m.

Steam generator level control loop f/2 Test IHP-136 n.

Emergency plant shutdown and cooldown indication Test IHP-146 o.

Reactor coolant flow Sdt II calibration Test IMP-200 p.

Pressurizer level Set II calibration Test IMP-209 No items of noncompliance or deviations were identifie.

Calibration of Safet Related Com onents Not S ecified b

Technical S ecification The inspector reviewed plant calibration records for the below listed components.

This review was performed to determine if the operating range/accuracy of components were consistent with applicable Technical Specification/SAR; the procedures used to calibrate the components were reviewed and approved as required by Technical Specifications; the procedures used contained acceptance criteria consistent w th Technical Specifications SAR; the procedures used contained detailed instructions commensurate with the complexity of the calibration and that the technical content of the procedures would result in satisfactory calibration.

a.

Plant Relay calibration Test IMP-014 b.

Electronic pressure transmitter calibration Test IHP-015 c.

Electronic alarm unit calibration Test IHP-020 d.

Level switch calibration Test IMP-027 e.

Temperature switch calibration Test IHP-028 f ~

Verification of relief valve set points Test IMP-029 g.

Emergency diesel excitation and voltage regulation calibration Test IHP-039 h.

Motor operated valve torque switches Test IHP-063 Pneumatic differential pressure transmitter calibration Test IHP-083 No items of noncompliance or deviations were identified.

7. 'he following instruments, gauges or other testing devices were inspected for current calibration, frequency and proper storage.

The calibration test is IMP-100.

Fluke Volt Meters 32003 32009 32020 32004 78458 73514 Fluke Di ital Volt Meters 320000 320040 320080 W&T Meters Heise Gau e

Transmitter Simulator TT 16296 CN P 210 6432 6560 1668 1168 1433 A

No items of noncompliance or deviations were identified.

-5-

e 8.

Safet Related Electrical Switch ear Test and Maintenance (Unit 2)

The inspector reviewed plant surveillance records for the below listed equipment.

This review was performed to determine if the surveillance test was covered by properly approved procedures; the procedures used contained functional testing of instrumentation used and acceptance criteria; operational checks prior to returning equipment to service were identified in the surveillance test; the technical content of the procedures would result in satisfactory testing; the procedures used contained acceptable trip settings for overload protection.

a.

Maintenance Inspection and Repair Procedure for 4KV Power Circuit Breakers (Procedure MHP 5021.082.002 Rev 2)

b.

Maintenance Inspection and Repair Procedure for Types K1600 and K16005 600 Volt Power Circuit Breakers (Procedure MHP 5021

.082.003 Rev 1)

c.

Maintenance Inspection and Repair Procedure for Type K600S 600V and 480V Power Circuit Breakers (Procedure MHP 5021.082.002 Rev 2)

d.

Maintenance Inspection and Repair Procedure for Air Circuit Breaker, Westinghouse Type DB-50/ (Procedure MHP 5021.082.012 Rev 0)

9.

Plant Tour The inspector conducted a tour of various areas of the plant to observe operations and activities in progress, general housekeeping and cleanli-ness, and equipment caution or lockout tags.

No items of noncompliance or deviations were identified.

10. Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)

at the conclusion of the inspection on December 20, 1978.

The inspector summarized the purpose, scope, and findings of the inspections.

No items of noncompliance or deviations were identified.