IR 05000498/1988044

Insp Repts 50-498/88-44 & 50-499/88-44 on 880705-08.No Violations or Deviations Noted.Major Areas Inspected:Review of Selected Open Items & Evaluation of Test Results for Control Rod Testing

ML20207B379
Person / Time
Site:	South Texas
Issue date:	07/26/1988
From:	Mckernon T, Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20207B377	List: IR 05000498/1988044 ML20207B374
References
50-498-88-44, 50-499-88-44, NUDOCS 8808020316
Download: ML20207B379 (5)

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lI APPENDIX l

U.S. NUCLEAR REGULATORY COMISSION  !

REGION IV l l

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NRC Inspection Report: 50-498/88-44 Operating License: NPF-76 ;

50-499/88-44 Construction Permit: CPPR-129 l Dockets: 50-498 l 50-499 Licensee: Houston Lighting & Power Company (HL&P)  ;

P,0, Box 1700  ;

Houston, Texas 77001

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Facility Name: South Texas Project (STP), Units 1 and 2 Inspection At: STP, Bay City. Texas  ;

Inspection Conducted: July 5-8, 1988 f

Inspector: -

Aw C 7/26//d i

/ 0.lMcferrion, Reactor Inspector, Test Date f VrograrEs Section, Division of Reactor Safety j i

I Approved: _ /w M 7 f, 0, 5fldTe, Chftf, Test Programs Section Dat'e !

Olvisich of Reactor Safety l l

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Inspection Sumary l

Inspection Conducted July 5-8, 1988 (Report 50-498/88-44; 50-499/88-44) {

i Areas Inspected: Routine, unannounced inspection of STP's Units 1 and 2 review l oT selected open items attd evaluation of test results for control rod testin l I

Results: Within the two areas inspected, no violations or deviations were identTTied, j HRSSEM Bul$y Q

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DETAll.S 4 Persons Contacted

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Principal Licensee Employees

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• Wisenburg, Plant Superintendent

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• S. M. Head, Supervisor Licensing Engineer M. Carnley, Instrumentation and Control Manager, Unit 1

, *M. Polishak, Licensing Engineer

D. Parker, Startup Engineer, Unit 2

*S. L. Rosen, General Manager, Operations Support

• J. D. Green. Manager, Inspection and Surveillance

• W. S. Blair, Maintenance Manager

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• M. A. McBurnett, Manager, Support Licensing

• R. Ferguson, Licensing Engineer l

• S. M. Dew, Operations Support Manager i

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R. Pate Nuclear Plant Operations Engineer

W. Evans, Licensing Engineer i

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• J. Bess, Resident Inspector, STP

• Denotes those personnel attending the exit intervie T

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! The NRC inspector also interviewed other licensee personne . Followup on Previous Inspection Findings (92701)

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j (Closed)OpenItem 498/8775-03. NRC Inspection Report 50-498/87-75; j

50-499/87-75 identified the licensee's omission of the CVCS system from ;

i the leakage reduction program as required by Technical i

Specification (TS) 6.8.3a. During the followup inspection, the NRC , !

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inspectorreviewedlicenseepositionletterST-HL-AE-2001datedMay(151)

1987, which included the CVCS system in the in-service inspection >

l program per ASME,Section XI requirements. Furthermore TS change  !

4 notice (TSC-44) was submitted via ST-HL-AE-2485 dated January 28, 1988, to I

omit the CVCS system from TS 6.8.3a. The licensee justified exclusion of !

I the CVCS system from the TS 6.8.3a and NUREG-0737 leakage reduction (

) program requirements by stating that the CVCS system was not needed for f L' shutdown in a postaccident condition and the letdown / seal leakoff and !

} charging portions of the system were isolated upon a containment isolation [

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signal. This matter had been discussed with the NRC and TSC-44 approve This item is considered closed.

l (Closed) Violation 498/8001-08. The violation involved inadequate

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corrective action in that the licensee had a backlog of overdue station I

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j problem reports (SPR). The NRC inspector reviewed the licensee's tracking l system for station problem reports. Through selective sarpling of SPRs,

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the NRC inspector verified that management is effectively tracking problem reports and that root causes are adequately addressed and documented. As  :

of July 1988, the NRC inspector verified that 4 of 246 station problem i reports were overdue. This quantity is a marked reduction from January 1988 when 68 of 204 SPRs were overdue for completion. This item is considered close ,

(0 pen)Unresolveditem 498/8809-0 The inspection finding addressed the question of satisfying TS 6.8.3 requirements to establish, implement, and maintain a program to reduce leakage from those portions of systems t outside the containment that could contain highly radioactive fluids i during a serious transient or accident. In review of licensee documents cited above and NUREG-0737, the intent of h' JREG-0737 leakage reduction  ;

program and TS 6.8.3 was to address those systems considered in the plant accident analysis which could act as radioactive materials effluent paths to the environment. Those systems outside the containment which are isolated during transient or accident conditions are excluded from the requirements of TS 6.8.3. TS 6.8.1 requires that written procedures shall be established, implemented, and maintained covering activities recomended in Appendix A of Regulatory Guide 1.33, Revision 2 of February 197 Regulatory Guide 1.33, Appendix A, states that written procedures should be developed for control of radioactivity (i.e., limiting materials released to the environment and limiting personnel exposure). As such, leakage control, minimizing personnel exposure, and minimizing boric acid corrosive attack on materials are of significant concerns to the license In discussion with licensee personnel, a program for monitoring leakages t in systems containing radioactive fluids outside the containment is being implemented. The tracking of leakages is based upon submittal of The t maintenance work requests (MWR) for the particular system.along leakage is classif with the contamination levels, status of the MWR, and other pertinent *

information. This information was maintained in a computer data base and reytewed weekly. The individual responsible for maintaining the data base r was also responsible for performing system walkdown inspections to verify the type of leakage, status, and prioritizing the problem to operations should the leakage become a significant concern. Although the licensee has implemented a program for leakage reduction outside the containment, the licensee has not formalized the program in a specific written  ;

administrative orocedure, which develops guidelines for the program's implementation, designation of responsibilities, trending, interfacing, and coordinating the program with other departments. In review of the data base, the NRC inspector noted a significant number of MWRs for i leakages in the CVCS syste Durin i mechanical auxiliary building (MAB)g a walkdown area, the inspection NRC inspector further of the j verified that numerous MWR tags were hung on the CVCS syste The  !

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licensee's development of a formalized leakage reduction program and procedure shall remain an open item pending future review for adequac ;

(498/8844-01)  !

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(Closed)OpenItem 498/8809-03. This osen item involved the licensee's j control of instrument valves. During tie follewup inspection, the NRC '

inspector discussed the instrument valve labeling program with the I instrtmentation and control maintenance manage Through review of I

, MWRs XC-87021200, XM-87023426, and XT-88006006, the NRC inspector verified j that the licensee has completed labeling instrument valves inside the ,

, reactor containment building and is currently labeling instrument valves

inside the mechanical / electrical auxiliary building (MEAB), class I vital  ;

compartments (IVC), and the turbine generator building. The NRC inspector l

. verified the above during a selected systems walkdown of the MEA This

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item is considered close (Closed)OpenItem 499/8816-02. This portion of the inspection involved a  :

review of RCS cold hydrotest results to verify that the stated objectives ,

! and acceptance criteria were met. The NRC inspector also verified the l test was adequately reviewed by the appropriate manage The test i

"as-conducted" satisfied the stated objectives and test data was within

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< the acceptance criteria of the procedures. The Itcensee's administrative i

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practices in the execution of the test, data evaluation, and resolving problems occurring during the test were adequate. This item is considered l

) ciosed, l 3. Control Rod System Tests (IP70532)

i During this portion of the inspection, the NRC inspector reviewed test results from the following procedures for Unit 2:  ;

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2RS-A-01, Revision 0, "CRDM Power Supply (Motor Driven Generator  :

Sets)"  !

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• 2RS-P-03, Revision 0, "Reactor Trip Switchgear"

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d r j The NRC inspector verified that stated test objectives and acceptance  !

criteria were satisfied. Deviations found during the test performance 1 j were properly and effectivaly resolved, i Within the scope of the inspection, r

0 violations or deviatiors were l identified.

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! 4 Exit Interview  !

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1 An exit interview was conducted with HL&P personnel on July 8,1988, at i i

the conclusion of the onsite inspection, during which the inspection I

findings were summarized. The licensee did not identify as proprietary j any of the naterials provided to, or reviewed by, the NRC inspector during i the inspection.

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Documerit Narnet -

EB103 f

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Requestor's ID: l

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OP20  :

Author's Name:

3 JGagliardo/cjg i ,

Occument Coments:

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