IR 05000458/1989022

Insp Rept 50-458/89-22 on 890525-27.No Violations or Deviations Noted.Major Areas Inspected:Containment Integrated Leak Rate Test & Review of Results of Local Leak Rate Test

ML20245C904
Person / Time
Site:	River Bend
Issue date:	06/20/1989
From:	Ray Azua, Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20245C889	List: IR 05000458/1989022 ML20245C887
References
50-458-89-22, NUDOCS 8906260322
Download: ML20245C904 (6)

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i APPENDIX U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

i NRC Inspection Report: 50-458/89-22 Operating License: NPF-47 Docket: 50-458 Licensee: Gulf States Utilities (GSU)

P.O. Box 220 St. Francisville, Louisiana 70775 Facility Name: RiverBendStation(RBS)

Inspection At: RBS, St. Francisville, Louisiana

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Inspection Conducted: May 25-27, 1989

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Inspector: + 4 /20 /W/

R. V. Azug/ Peactor Inspector, Test Programs Date /

Section,DivisionofR$actorSafety

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Approved: -1

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. C. Seidlet) Chief, Test Programs Section Date Division of Rdactor Safety Inspection Summary Inspection Conducted May 25-27, 1989 (Report 50-458/89-22)

Areas' inspected: Routine, announced inspection of the River Bend Station ;

containment integrated leak rate test (CILRT) and a review of the results of l

.the local leak rate test (LLRT).

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Results: Within the two areas inspected, no violations or deviations were identified. CILRT and administrative procedures were reviewed with weaknesses identified in the CILRT procedure with regard to the tagging process. A plant walkdown was performed and a portion of the valve lineup was reviewed along with the controlled copy of the test procedure. No concerns were raised, but .

an observation was made with regard to the tagging process (i.e., two different !

types of tags were used). The LLRT results were reviewed. Two service water system isolation valves and their associated check valves were found to exceed the .60 La combined limit as stated in 10 CFR Part 50, Appendix J. The ,

licensee was not able to quantify this leakage; therefore La was exceede l The licensee has repaired the. valves and reduced the combined leak rate to i less than .60 L ADOCK0500gg8

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DETAILS i Persons Contacted

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- GSU ,

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'*M. Feitner, Licensing Engineer F. Odem," Instrumentation and Controls Technician, First Class

• J. Cook, Lead Environmental Analyst

• G. Siry, Senior Engineer, Field Engineering, CILRT Test Director-

• A.' Kugler, Process System Supervisor, Field. Engineering

• M. Sankovich, Manager,' Engineering

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Stone & Webster

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• H. Thickman, Contract Engineer, CILRT Test Support NRC E. J. Ford, Senior Resident Inspector

• Denotes those present during the exit interview held on May 30, 198 The NRC inspect'or also interviewed other licensee' employees during the .

course of the inspection.- CILRT Procedure Review (70307)

The NRC inspector reviewed Procedure No. STP-057-3703, Revision 1,.

" Primary Reactor Building Integrated Leak Rate Test."

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The NRC inspector reviewed the procedure to verify that the. licensee had incorporated the associated regulatory requirements and commitments. In-addition, the_ procedure was verified to have the proper approvals, as indicated by appropriate signature The NRC inspector chose some randomly selected systems (reactor water cleanup. discharge'and service. water), which were addressed in Procedure ;

No. STP-057-3703, Attachment 19. for review against-the licensee's' piping /

and instrumentation. diagrams (P& ids). This was done to determine with reasonable assurance, that all the appropriate valves in the selected systems were addressed in the procedure. The NRC inspector also reviewed the test position of the valves, listed in the same procedure, to verify that the associated systems were placed in correct alignment for the performance of the CILR The CILRT procedure gave the licensee the option to either perform the

? 24-hour, Type A. Total Time Test, as described in ANSI N45.4-1972,

" Leakage Rate Testing of Containment Structures for Nuclear Reactors,"

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-3-t I (datedMarch 16,~1972) or, under favorable conditions, the' licensee'may-

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perform a. reduced time test, using the methodology described in Bechtel Topical Report BN TOP-1. The NRC inspector-reviewed the options andLfound-them to be technically adequat ~

O The NRC inspector. reviewed.the temporary changes that were made to

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Procedure No. STP-057-3703, and~found them to be acceptable. .The licensee

'.did not alter the technical content of the procedure or change the way in t which the test was being performed. The NRC inspector also. verified that these changes were . approved, as indicated by the appropriate signature During-the review of Procedure No. STP-057-3703, the NRC inspector noted that GSU.'s Administrative Procedure No. ADM-0027, " Protective Tagging,"

was listed as a reference document. This administrative procedure listed the criteria for,using " DANGER" tags, and required that. plant. personnel have proper. authorization prior to removing these tags or altering the:

position of the tagged equipment. -The NRC inspector noted that this reference:

was:not. addressed in the' body of the procedure and that there were no-direct' reydrements for any of the valves or- equipment to be~ tagged prior to or during the performance of this test.- In addition, it was:also noted '

. that although Attachment 19. "ILRT Valve Lineup," had a- signoff for valve positicn verification, there was no methodology identified on.how this verification was to be performed. It is imperative that during the performance of the'CILRT' test, all the proper systems be subjected to the test pressure, and that there are no systems that are masked due to

. inadvertent valve closure or inadequate valve alignment. One method used to assure this is'the tagging process, with a'well defined independent verification program. The valve alignment program described in CILRT Procedure No. STP-057-3703 was vague in the area of verification and _

tagging and was open to interpretation (i.e., tagging could be considered .

optional,'with full faith'being placed on the; operators and other plant personnel to identify the valves being.used in the test). The NRC inspector found this to be a weakness in the CILRT progra No violations or deviations were identified in the review of this program are . CILRT Surveillance (70313)

The NRC. inspector performed several tours of the containment, the drywell and the auxiliary building. This was done to inspect the test equipment installed for the CILRT and to monitor the valve lineup proces The valve lineup process was performed using Attachment 19 to Procedure No. STP-057-3703, along with other sections of the procedure. The NRC inspector noted that two types of tags were being used for the CILRT valve alignment.,. One' type was the " DANGER" tag, which was covered in Administrative

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-4-E Procedure No..ADM-0027, and the other type was the " CAUTION" tag,.which was covered in Plant. Engineering Procedure No. PEP-0045. The " CAUTION" m tag procedure was not listed as a reference document in the CILRT procedure, nor was it addressed in the body of the procedure. The determination as to which valve received _which tag was at the discretion of the CILRT test coordinator. Both sets of tags identified the valve number, the condition.-

in which the valve was_-required to be positioned, and contained the signatures of the installer and of the independent verifie The NRC inspector reviewed both tagging procedures,'ADM-0027 and PEP-0045, to determine the.. effectiveness of this tagging process. The NRC inspector found the tagging procedures to be acceptable and that the tags were

. easily recognized by the plant personnel who had been trained on the meaning of these tags. The NRC inspector made the observation that the criteria for the " DANGER" tag was more restrictive than for the " CAUTION"

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tag, and that using only one type of tag for the test may be less confusin The NRC inspector reviewed a sample of 56 valves that had,been positioned and tagged for this test; no errors or discrepancies were note The calibration documentation for the resistsit temperature detectors (RTD)

used in the CILRT (provided by PYC0) were reviewed by the NRC.insnecto The RTDs were found to be in calibration for the period encompassing the

tes The NRC inspector accompanied the licensee on a final walkdown of the drywell on May 27, 1989. It was noted that all pressure retaining vessels such as. fire extinguishers and aerosol cans had been removed.. There were trash bags, plywood in the containment hatch, and pieces of equipment such as desks, fans, and hoses that still remained in the drywell. The licensee stated, with reference' to the combustible materials, that any fire would be detectable through the RTDs that were in place for the test, and that a drywell or containment entry to suppress the fire would be possible because of the low pressure conditions (8.6 psi) of the tes The personnel airlock to the drywell was closed, and the initiation of the containment pressurization was done on May 27, 1989. The NRC inspector reviewed the licensee's controlled copy of Procedure STP-057-3703, to

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verify that the proper sections had been signed off, and that all the prerequisites had been me In addition, the NRC inspector reviewed the I test station log The CILRT was completed on May 29, 1989, and based on the preliminary

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data, no leakage was detected that appeared to exceed the .75 La limit, I

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identified in Chapter 10 of the Code of Federal Regulations, Part 50, {

Appendix J. The NRC inspector will perform a review of the results when q

- the final report is issued. The results of this review will be documented  ;

in a separate NRC repor {

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D f - No ' violations or deviations were. identified in the review of this progran are . Containment Local Leak Rate Testing (LLRT)(61720)

The NRC inspector reviewed the LLRT data that was obtained prior to and during the preparation for the CILR Based on this data, two service water system isolation. valves, identified as-SWP MOV 507A and SWP MOV 507B~, and their associated check valves', were identified as having exceeded the .60 La combined ' limit identified in .

Chapter 10 of the Code of Federal' Regulations Part 50, Appendix J. The licensee was unable to quantify the. leakage involving these valves; therefore, La was exceeded.. The licensee stated to the NRC ' inspector that- the . valves had been . repaired before the CILRT and the combined leak rate was reduced'to less than .60 La. (LER89-11, Revision 2, which addresses this matter has been issued by the licensee.)

No ' violations or deviations were identified in the. review of this program'

are ' Exit Interview Because of the time constraints and availability of personnel, the exit interview was; conducted by telephane on May 30, 1989. The NRC inspector summarized the scope and findings of the inspection. The licensee did not' identify as proprietary any of the information provided to, or reviewed by, the NRC inspector.

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