IR 05000498/1989001

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Insp Repts 50-498/89-01 & 50-499/89-01 on 890109-13 & 23-27. No Violations or Deviations Noted.Major Areas Inspected: Calibr Program & Preventive Maint Program Re Calibr of Plant Instrumentation for Components Not Addressed in Tech Spec
ML20236C476
Person / Time
Site: South Texas  
Issue date: 03/09/1989
From: Andrea Johnson, Stetka T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20236C472 List:
References
50-498-89-01, 50-498-89-1, 50-499-89-01, 50-499-89-1, NUDOCS 8903220173
Download: ML20236C476 (9)


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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION L

REGION IV

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i NRC Inspection Report:

50-498/89-01 Operating Licenses:

NPF-76

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50-499/89-01 NPF-78 j

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Dockets:

50-498

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_50-499 l

' Licensee: Houston Lighting & Power Company (HL&P)

Ll P.O. Box 1700

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Houston, Texas 77001

Facility Name: South Texas Project, Units I and 2'(STP)

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Inspection At:

STP, Matagorda County, Texas Inspection Conducted: January 9-13 and 23-27, 1989 Sk/M Inspector:

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A. R. Jbhnson, Reactor IMspector, Plant Systems Date Section Division of Reactor Safety'

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$ [9!'[rf Approved:

Mffik T. Stetta, Chief, Plant Systems Section Date

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Division of Reactor Safety

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Inspection Summary

Inspection Conducted January 9-13 and 23-27, 1989 (Report 50-498/89-01)

~ Areas Inspected: Routine, unannounced inspection of the licensee's Technical 4 Specification (TS) required calibration program, and the preventive maintenance (PM) program related to the calibration of plant instrumentation

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for components not addressed in the TS.

Results: Within the areas inspected, no violations or deviations were identified.

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The licensee's plant surveillance (PS) calibration program for the control and evaluation of installed instrumentation and control (IAC) devices, specified by

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the TS is effectively being implemented and no weaknesses were noted.

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-2-An apparent weakness was identified, however, in the licensee's calibration program for I&C devices not addressed in the TS. The apparent weakness involves a lack of procedural controls which resulted in a large number of installed I&C device calibration deferrals. This issue has been identified as an.aresolved item.

Inspection Conducted January 9-13 and 23-27, 1989 (Report 50-499/89-01)

Areas Inspected:

No inspection of Unit 2 was conducted.

Results: Not applicable.

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I DETAILS 1.

Persons Contacted l

HL&P_

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    • W..H. Kinsey, Plant Manager

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    • M. R. Wisenburg, Plant Superintendent ~, Unit 1-
    • S. L..Rosen, General Manager,. Operations Support

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    • S. M. Dew, Manager, Operations Support

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    • G. E. Vaughn, V.P. Nuclear Operations l
    • M. A. McBurnett, Licensing Manager
  • P. L. Walker, Senior Licensing Engineer l
  • K. L. Trippel, Lead Engineer i
  • R. Fast, Instrumentation & Control (ISC) Maintenance
  • S. M. Head, Supervisor, Licensing Engineering
    • W. J. Jump, Maintenance Manager
    • M. H. Carney, I&C Supervisor
    • J. L. Lewis, I&C Technical Supervisor

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    • S. E. Hill, Maintenance Support Administrative Supervisor
    • R. A. Ferguson, Licensing Engineer.

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    • W. P. Morgan, Manager, Materials Laboratory J. E. Noftsger, I&C. Technical Supervisor W. H. Humble, Programs Supervisor R. Grantom, I&C Technical Department J. Wallace, Outage Department i

J. Geiger, General Manager, Nuclear Assurance

.l R. Balcom Quality Assurance, Operations

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NRC

    • J. E. Bess, Senior Resident Inspector, Unit'1'
    • R. J. Evans, Resident Inspector, Unit 1 -

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  • Attended exit interview on January,13, 1989.
    • Attended exit interview on January ~27,:1989.

The NRC inspector contacted other licensee personnel during the inspection, i

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Calibration of Plant Instrumentation (56700)

This inspection was to accertain whether the licensee had developed and

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implemented a program for the calibration and testing of plant installed I

I&C devices. This includes the I&C devices specified in the Technical'

Specification (TS) and-I&C devices that are used for the operation and testing.

of equipment but not specifically addressed in the TS as requ' iring

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calibration.

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2.1 Calibrations Specified by TS Calibrations required by TS are controlled as part of the STP Plant Surveillance (PS) Program. The inspection determined.that procedures for calibration of plant. installed I&C devices, specified by.TS, are being implemented in accordance with the calibration program administrative-i

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controls, as prescribed by the STP FS/.R. Sections 7.0 and 17.2, and related commitments to Regulatory Guides and Standards. The TS surveillance program data base is well established and re flects.the status.of. all planned 'in-plant

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surveillance tests and inspections. This schedule.is outlined in STP Operations QA Plan - Instrumentation and Calibration Control (QAP),

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l-Section 12, phragraph 6.1, and STP Plant Procedures Manual.(PPM)

l OPG P03-ZM-0016, Revision 1.

Technical Specification surveillance and

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calibration requirements'are further controlled by Procedure OPG P03-ZE-0004, Revision 2, and together with the QAP include requirements-that verify

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completion of, surveillance tests.and inspections required by the TS.

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The NRC inspector verified that installed I&C device channel calibrations (CCs), analog channel operational tests (ACOTs), trip l

actuating device operational tests (TAD 0Ts), actuation logic tests (ALTs),

master / slave relay tests (MRTs/SRTs), and response time tests (RTTs),

specified by the TS were performed.at the required frequencies. The NRC inspector used the TS Surveillance Program Data Base for STP-1 dated January 11, 1989.

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l The NRC inspector examined completed test and calibration procedures (documentation packages) for surveillance performed during the last 18 months. This review verifiedi (1) test documentation was complete; (2) approved procedures were utilized; (3) acceptance criteria were met; (4) performance was in accordance with the procedures; and (5) completed procedures contained "as found" conditions.

The specific documentation packages examined by the NRC' inspector are listed below:

Engineered Safety Features Actuation System (ESFAS) Instrumentation Surveillance Requirements

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Procedure No.

Revision No.

. Title 1 PSP 02-SP-0004-1

ESF Manual Initiation, TADOT 1 PSP 03-SP-0005R

SSPS Train Logic, Train R ALT IPSP03-SP-0007A-1

SSPS Train A, MRT IPSP03-SP-0008A-1

SSPS Train A, SRT 1 PSP 05-RC-0455-1

Pressurizer Pressure Set 1. CC 1 PSP 02-RC-0455-1

Pressurizer Pressure Set 1, ACOT

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-5-IPSP05-MS-0514-1

Steam Pressure Loop 1 Set 1, CC IPSP02-MS-0544-1

Steam Pressure Loop 4 Set 1, ACOT IPSP02-MS-0524-1

Steam Pressure Loop 2 Set 1, ACOT 1 PSP 02-HC-0936-1

Containment Pressure Set 2, ACOT IPSP05-HC-0935-1

-Containment Pressure Set 3, CC 1-SP-P-03

Solid State Protection System, RTT, Credit Package (for 1 PSP 13-HC-0934, 0935, & 0936)

1-SP-P-03

Solid State Protection System, RTT, Credit Package (for IPSP13-RC-0465, 0466, 0467,

& 0468)

Reactor Trip System (RTS) Instrumentation Surveillance Requirements Procedure No.

Revision No.

Title 1 PSP 02-RC-0420-1

Delta T and T Average Loop 2 Set 2, ACOT IPSP05-RC-0410-1

Delta T and T Average Loop 1 Set 1, CC 1 PSP 02-RC-0465 1

Pressurizer Level Set 1, ACOT IPSP05-RC-0465-1

Pressurizer Level Set 1, CC IPSP02-RC-0481-1

RCS Flow Loop 1, Set 2, ACOT 1 PSP 05-RC-0418-1

RCS Flow Loop 1, Set 2, CC IPSP03-SP-0006R-1

Train R Reactor Trip Breaker, TAD 0T The NRC inspector made the following observations with regards to the licensee's PS program:

2.1.1 RTT Procedures Data packages were prepared by HL&P, using preoperational test data prior to station startup of STP-1, in lieu of RTT requirements by TS.

Many RTT procedures for frequencies of 18-months and greater, have l

not yet been issued.

At the tine of this inspection, 207 out of I

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approximately 1000 RTT procedures still remain in draft form.

These procedures will be issued at STP-1 prior to the first TS required RTT period.

2.1.2 CC Procedures Preoperational test data packages for STP-1 were used in lieu of. CC procedures to meet initial CC surveillance requirements. The CC surveillance were short-period calibrations which have since been

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accomplished using newly issued CC procedures. The NRC inspector estimated that 10 percent of STP-1 CC surveillance were performed, taking credit for test data packages.

2.1.3 ACOT, TADOT, ALT, MRT, and SRT Procedures All initial and' subsequent ACOTs, TAD 0Ts, ALTs, MRTs, and SRTs-for STP-1 are being. accomplished using issued surveillance procedures.

No' violations or deviations were identified.

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2.2 Calibrations Not Specified by TS The programmatic controls for the calibration of installed I&C devices used at STP for safety-related/ quality-related applications, associated:

but not addressed in the TS, are part of the STP preventive maintenance (PM)

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l Program. These instruments are used during surveillance testing and -

operation of safety-related equipment and are referred to in the STP plant routine operating procedures.

The schedule of calibration and verification for these insta11ed'I&C devices is outlined in the STP QAP, Section 12 and

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l Procedure No. OPGP03-ZM-0002, Revision 16. "PM Program."

HL&P has accomplished an engineering review of some 7000 safety-related/

quality-related instrument devices to determine their requirements with regards to PM calibration activities.

HL&P has established an approved and active PM list of approximately 1500 instrument devices based on the following criteria:

HL&P reviewed the Architect Engineer's (Bechtel's) instrument index

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HL&P reviewed all STP routine operating and surveillance procedures and included all instruments contained in these procedures on the

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approved PM list.

HL&P accomplished an engineering review of the STP main control room

and included all these instruments on the approved PM list.

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The.NRC inspector reviewed the licensee's implementation of Procedure OPGP03-ZM-0002 to ascertain whether calibration of'the, selected-

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instrument devices in the.PM program were~being accomplished effectively.

d-The NRC inspector reviewed the licensee's PM Schedule. Data Base,L ated

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January 25, 1989.' The data base.is used by HL&P to prioritize:the scope and frequency of the required PM calibration activities. - The NRC -

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inspector. sampled PM data packages listed on the data base-for::

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(1) backlog of past due calibrations; (2) reasons' for deferrals, inactivations,.and cancellations; (3) availability of approved procedures.

for calibration of instrument devices; and.(4) examination of technical

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content. The sample PM data packages were limited to instrument device calibrations performed by the maintenance. I&C division. - The-followingL is a list of PM procedures reviewed:

PM No.

Description Fre-Due

- Da'te quency Fate TerTormed (Weeks)

IC-1-AS86011921=

Calibration, Aux Steam

05/29/89 10/14/88

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To LWPS, HELB A Protection (Tag #A1ASPDSH8838A)

IC-1-CH-86009893 Calibration, ECHW Train A, 24'

05/01/87

Chiller VCH004, Compressor Discharge (Tag # NICHPI9504B)

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IC-1-CH-86009895 Calibration, ECHW Train A,

01/27/89 07/01/88 I

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Chiller VCH004, Compressor

1 Suction Pressure l

(Tag # NICHPI9504A)

f IC-1-CH-86009896 Calibration, ECHW Train A,

.05/01/87.

Chiller VCH004, Compressor

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Lube Oil Pressure (Tag # NICHPI9504)

IC-1-CH-86009900 Calibration ECHW Train C, 24:

02/07/89 07/12/88 Chiller VCH006, Compressor Lube Oil Pressure (Tag # NICHPI9516)

fC-1-CH-86009902 Calibration, ECHW Train C,

02/07/89 07/12/88 ~

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Chiller VCH006, Compressor

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Suction (Tag # NICHPI9516A)

l-IC-1-CH-86009903 Calibration. ECHW Train C,~.24 02/07/89 07/12/88 Chiller VCH006,' Compressor Discharge Pressure (Tag #NICHPI9516B)

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'IC-1-CH-86009909-Calibration, ECHW Train B,

12/01/88 05/05/88 Chiller VCH005, Compressor Lube Oil Pressure (Tag # NICHPI95108)

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.IC-1-CH-86009911 Calibration, ECHW Train B,

-12/01/88 05/05/88 Chiller VCH005, Compressor Suction Pressure (Tag # NICHPI9510A)-

L TC-1-CH-86009913 Calibration ECHW Train B,

12/01/88 05/05/88-Chiller VCH005, Compressor.

l Discharge Pressure (Tag # NICHP19510)

1C-1-CH-87011946-Calibration, Mild

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Environment, ECHW Train A, Chiller.VCH004, Purge High-Pressure (Tag # AICHPSH9533)

IC-1-CH-87011947 Calibration, Mild

'26 06/09/89 10/25/88 Environment, ECHW Train B, l

Chiller VCH005, Purge High l

Pressure (Teg # B1CHPSH9534)

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IC-1-CH-87014078 Calibration, ECHW Train A,

07/04/88

Chiller VCH004, 011 Heater-Thermostat (Tag #A1CHTSH9435)-

IC-1-CH-87014080-Calibration, ECHW Train C,.45 12/22/88

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Chiller'VCH006, 011 Heater Temperature (Tag # ICHTSH9437)

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l IC-1-DG-86003021 Calibration, Diesel

03/27/88

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Generator #11, Engine Speed (Tag # AIDGSI5476B)

-IC-1-D0-86007536 Calibration, Diesel

03/27/88.

  • 1 Generator #11, Fuel Oil Drain Tank (Tag # AIDOLSHL5470)

IC-1-EW-86002645 Calibration, Diesel

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Generator Heat Exchanger Outlet Temperature, Train A

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'(Tag # A1EWFT6855)

IC-1-EW-86003348-

' Calibration, CCW Pump

'09/23/88

Cooler Outlet, Train A (Tag # A1EWFT6856)

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TC-1-MS-860011155 Calibration, Steam:

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10/04/89

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Generator-ID, PORV High

. 1 Hydraulic Pressure (Tag'f 01MSPSH7441)

IC-1-MS-86011156 Calibration. Steam-78-10/04/89

Generator ID P Low

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(Tag # D1MSPSL7441).

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  • The NRC inspector determined that' the PM' data' packages were complete;

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i acceptance criteria had been met; the proper approved test procedures.had been

l used; and technical contents were-acceptable.- However, the.NRC inspector

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performance. The backlog _of past.due calibrations appeared to.be-a' result ~

of inadequate procedural controls atiSTP resulting,in a(failure to meet.

required calibration frequencies as outlined by Procedure OPGP03-ZM-0002.

The NRC inspector discussed the backlog of past 'due calibrations; problem with, the licensee and determined that the-licensee had identified this issue and

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was in the process of taking appropriate and timely corrective action. This

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i issue is considered to be an unresolved: item ~pending. correction by the licensee and subsequent review by the NRC..

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Unresolved Item (498/8901-.01):. Complete corrective. actions.to pr' event overdue

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calibrations of instrumentation not specified by the TS.

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Exit Interview i

The inspection scope and findings were. summarized on January 27, 1989, with the licensee personnel indicated in paragraph 1 above. The licensee did not identify as proprietary any of the materials:provided to or reviewed by the NRC inspectors during the-inspection.

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