IR 05000348/1990021

Insp Repts 50-348/90-21 & 50-364/90-21 on 900709-13.No Violations or Deviations Noted.Major Areas Inspected:Areas of Local Leak Rate Testing & Review of Previous Insp Findings.Five Open Items Re Leak Rate Testing Closed

ML20058P871
Person / Time
Site:	Farley
Issue date:	07/30/1990
From:	Belisle G, Whitener H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20058P870	List: IR 05000348/1990021 ML20058P866
References
50-348-90-21, 50-364-90-21, NUDOCS 9008210003
Download: ML20058P871 (6)

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Report Nos.: 50-348/90-21 and 50-364/90-21 ,

Licensee: Alabama Power Company-600 North 18th Street - '

Birmingham, AL 35291-0400 i

Docket Nos.: 50-348 and 50-364 License Nos.: NPF-2 and NPF-8-

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Facility Name: - Farley 1 and'2 -

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Inspection Conducted:- July 9 ,13, 1990 1 Inspector: W$, /t $1Nau 7-27 J9n ,

H.1.Whiteney Date Sigt.Cd I Approved by: %v r 7 o[#d'

G. A. Belisle, C?tief Date Signed Test Programs Section'-  ;

Engineering Branch

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Division of Reactor Safety  !

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SUMMARY l t

Scope: ,'

i This routine, unannounced inspection was conducted in-the areas of local leak rate testing and review of previous inspection finding q Results:

Review of ~ portions of- the local ' leak rate test: procedures,:-selected ' test '

results and test performance' indicates that adequate test procedures have.been-developed and implemented _and that local' leak rate testing .has been performed 1 in compliance with the regulations. Five^ open items ~ in the area of -leak _ rate  !

testing were close si In the areas inspected, violations.o ideviations:were not-identifie ~

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i REPORT DETAILS l Persons Contacted Licensee Employees

• R. Berryhill, System-Performance Manager L. Bonds, Nuclear Technician

• S. Casey, System Performance Supervisor-D. Hartline, General Plant Engineer' . ,

R. Marlow,. Plant Supervisor, Technical- 1

• D. Morey, General Manager, Farley Nuclear Plant NRC Resident Inspector

• Maxwell, Senior Resident Inspector I

• Attended exit interview Acronyms and initialisms used throughout this report are listed in th ,

last paragrap ,i Leak Rate Program (6172ri ll The. purpose of this inspection was to review the status of previous inspection findings in the area of h 4 ce testing and necessarily involved review of cortions of the lea' . ate program including:-

Local leak rate test procedures, FNP-1-STP-627 and FNP-2-STP-62 Unit .1, Containment Integrated ueak - Rate Test-.-(CILRT)' Report, . -

l November 1986

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Unit 2, Containment Integrated Leak Rate' Test -(CILRT) Report, '

November 1987 1 Selected data from the leak' rate test log Selected penetration drawings  !!

The selected portions: of the licensee's program were reviewed for o conformance with 10 CFR 50, Appendix J. Primary Reactor Containment y Leakage Testing For Water-Cooled Power Reactors; ANSI-N45.4', Leakage-Rate ,

Testing of Containment Structures for Nucleer Reactors; FSAR Section 6, '

Tables 6.2-39, 6.2-38, and 6.2-31; and. TS Section-4.6. In review of test procedures, data collection test results, and - test performance no violations or deviations were identifie With regard to previous inspection findings,- five items related to leak rate testing were close l

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! Action on Previous Inspection Findings (92701, 92702) -

, (Closed) Violation (50-348/86-25-01): Failure to Measure Change In Leak Rate Resulting From Repairs or Adjustments To The Contain. ent Boundary Prior To The Type A Test In Order To Determine The Overall  ;

Containment "As Found" Leek Rat ,

The above violation was identf fied during a review of the licensee's local (Type C) leak rate test program in 1986 where the inspector ,

identified that two components, the equipment hatch and fuel transfer tube flange, were subjected to manipulations considered to be rep 61rs or adjustments without first obtaining an "as found" leak rate. In that review, the inspector determined that, with the exception of l

these two components, the licensee had developed procedures and test

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controls and was performing an adequate "as found" leak rate test r ogra Consequently, the violation for failure to obtain an "as found" leak rate for these two components, while considered a violation of 10 CFR 50 Appendix J and ANSI-N45.4, was not of major safety significanc In this inspection, the inspector reviewed portions of the local leak rate test procedures, FNP-1-STP-627, Revision 15; FNP-2-STP-627, Revision 2?; data from the local leak rate test log; and, Type B & C leak rate test results in the integrated leak rate test report for Unit 1, November 1986 and Unit 2, November 198 This review showed that the licensee's "as found" leak rate program included the equipment hatch and fuel transfer tube flange. The inspector concluded that the licensee las (2 velo)ed and implemented test procedures and test controls which .

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meet tie requirements of the'TS, 10 CFR 50 Appendix J, and ANSI-N45.4 l in this are . (Closed) IFI (50-348/86-25-02):- Evaluate ThelLicensee's Leak Rate

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Test Report For The Status of Containment Overall Leakage ,

In the November 1986 inspection the inspector determined on the basis  !

, of -data available that, excluding the equipment hatch and fuel transfer tube flange leakages, the overall containment leakage was about 0.07 wt. percent per day (based on Type A test measured leak rate of 0.054 wt. percent per day). This Ic?t a margin of 0.04 w ,

percent per day between the as found leak rate and the 0.75 La allowable leakage limit. The margin of 0.04 wt. percent per day l

equates to about 67,000 secm. Review of the licensee's integrated leak rate report of November 1986 for Unit 1 showed that these l estimates were correct. The as left leak rate prior to the 1986 R'0 r for the equipment hatch and transfer tube flange was 3.1 and 7.6 scem respectively. Review of as found/as left leak rates for these compor,ents since the 1986 Unit 1 RF0 (5 tests for both units) show 3 that as found leakage has been in a range of 10 to 40 scem for the equipment. hatch and 1 to 30. scem for the fuel transfer tube flang These numbers are insignificant relative to the estimated 67,000 seem

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margin and lend support to the estimated overall containment leakage of 0.07 wt. percent per day which is within the Appendix J acceptance limit of 0.1125 wt. percent per day. The inspector concluded that there is reasonable assurance that the overall contair. ment "as found" leak rate was acceptable in the Unit 1 1986 RF0. Hewever, the regulatory requirement is to demonstrate that leakage is ccceptabl Recurrence of this type of problem will be prevented by the current local leak rate test progra The next Type A test for Unit 1 is scheduled for November 1990, c. (Closed) IFI (50-348/86-25-03): Verify That Type C Leak Rates Are Added To The Type A Leak Rate Result For Penetrations 56, 57, and 46 In Inspections Report Nos. 50-348/86-25 and 50-364/86-25 the inspector identifiej that the valve alignments for penetrations 56, 57 and 46 were not correct for the Type A test. A review of the reasons for these abnormal test alignments showed that the alignments were justified from an operations aspect if the Type C leakage rate for these penetrations was added to the Type A test leak rate. A review of the CILRT report for the Unit 1 November 1986 Type A test showed that as loft minimum pathway Type C leak rates for penetra-tions 56, 57, and 46 were added to the Type A leak rate result to obtain the final test resul The inspector also reviewed the CILRT report for the Unit 2 Type A test of November '47 The Type C as left minimum pathway leakage far penetration 46 i added to the final Type A test result. Due to dif'erences in vab s arrangements between Unit I and Unit 2, p?r.etrations 56 and 57 were correctly aligned in the Unir 2 Type A teat and a Type C leak rate penalty was not require The inspector reviewed the Unit 2 valve alignment for penetrations 56 and 57 and concurs with the licensee's' pbs'itio The inspector also verified that any abnormal penetration alignments duringsthe -Type A test was identified in an appendix to,the Type A tes.t procedurf. The efore, addition of the Type C leak rate will be

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identified for each Type A test, (Closed) IFI (50-348/86-25-04): Resolve Appropriate Testing of Isolation Valves Q1E21V116A, B, and C

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Valves Q1E21V116A, B, and C are located outside containment in the reactor coolant pump seal. water supply lines penetrations 25, 26, and 2 FSAR Table 6.2.38 identifies these penetrations for Type C testing but the penetrations may remain full of water for the tes FSAR Table 6.2-39 identifies Q1E21V116A, B and C as containment isolation valves but references Note 4 in FSAR Table 6.2-3 Table 6.2-31, which lists penetrations, valves, valve locations and valve types, does not identify an outside isolation valve for oenetrations 25, 26 and 27 but does reference Note ~

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Note 4 of FSAR 'jble 6.2-31 in reference to valves Q1E21V116A, 1 B and C in pen.trations 25, 26 and 27 states the following: j

The seal water injection lines are considered as Open paths :

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post-LOCA. The high pressure in-flow through these lines during l the injection and recirculation phase precludes containment to atmospheric leakage. In the event that no in-flow is provided l through these lines (via operator action) the check valve

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nearest the containment would provide the first barrier and the manually operated needle valve contained in the seal injection -

line outside the containment would provide the second barrie :

Isolation of these lines should be required only for ,

maintenanc The 'inplication is that these valves are act in a potential air i leakage path and neeo not be Type C tested; yet FSAR Table 6.2-39 defines these valves as containment isolation valves and Table 6.2-38 i requires a Type C test with the penetrations water fille :

The conflict in FSAR statements was incorrectly identified in NRC Inspection Report No. 50-348/86 25 and 50-364/86-25 for resolution between Region II and NRR. Resolution of the intent of the FSAR test requirements is more appropriately the licensee's responsibilit At the exit interview -licensee management agreed to evaluate the :

system design with regara to Type C leak rate test requirements and revise the FSAR as appropriate to clarify the test requirements for valves Q1E21V116A.. B, and The- licensee's evaluation and corrective actions will be reviewed during future inspection i

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= (Closed). IFI (50-348/86-25-05) Resolve with NRR The Correct Method -

For Type C Testing Penetrations in FSAR Table 6.2-38 Identi'ied As AirTestsWithWaterFilledSistem ,

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The inspector reviewed the ' licensee's test program and concluded that the licensee is testing in accerdance with the NRC approved program described in FSAR Table 6.2-:18 . Consequently, there is no issue between the NRC and the licensee in regard to the-test method ,

used for the 16 penetrations descrfbed as Type C tested with a water filled system. Since this item did not specify licensee action, the inspector closed the item.' Any further review of these penetrations .

e.nd test methods will be in'.ernal to the NR *

4. Exit Interview The inspection scope and results were summarized on July 13, 1990, with those persons indicated in paragraph 1. The-inspector described the areas

, inspected and discussed in deta"1 the inspection results listed abov !

Proprietary information is not contained in this repor Dissenting

, comments were not received from the license ,

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The licensee was informed that the following open items were closed:

. Violation 50-348/86-25-01

IFI 50-348/86-25-02 IFI 50-348/85-25-03 ,

IFI 50-348/86-25-04 IFI 50-348/86-25-05 Acronyms-and Initialisms ANSI American National Standards Institute  !

CFR Code of Federal Regulations L

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CILRT Containment Integrated Leak Rate Test  :

FSAR Final Safety Analysis Report  !

IFI Inspector Followup Item '

NRC Nuclear Regulatory Commission RF0 Refueling Outage i SCCM Standard Cubic Centimeters per Ninute *

l T5 Technical Specification Type A Test Containment Integrated Leak Rate Test i

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Type C Test Containment Isolat. ion Valve Local Leak Rate Test W Weight 1,

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