ML19346A077

Environ Qualification of Safety-Related Electrical Equipment,Ie Bulletin 79-01B, Technical Evaluation Rept

ML19346A077
Person / Time
Site:	Farley
Issue date:	11/14/1980
From:	Merriweather N, Ruff A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19346A074	List: ML19346A073 ML19346A075 ML19346A076 ML19346A077
References
IEB-79-01B, IEB-79-1B, NUDOCS 8106050004
Download: ML19346A077 (64)

Text

_

G ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPME.NT II.B 79-011:

TECHNICAL EVALUATION REPORT DOCKET NO. 50-348 PLANT: Joseph M. Farley Nuclear Plant, Unit 1 DATED: November 14, 1980 Licensee: Alabama Power Company lype Reactor: Pressurized Water Reactor 1

1 Prepared by:

N. Merriweather YlW r

Engineering Support Section No. 1 Reactor Construction and Engineering Support Branch, RII i

810605OCA%

,. _ _ -, _ _ _ _ _ _ _.... _. _.. -.,,,.... _ _ _. _ _ _ _ _ _ _ _. _ _, -... _.. _.. -.. _ _ _ ~ _.,.. _...

TABLE OF CONTENTS F/.GE $0.

1.

INTRODUCTION.................

I 1.1 General..................................................

I 2.

BACKGROUND AND DISCUSSION.........................................

1 2.1 General....................................................

I 2.2 On-Site Inspection.........................................

2 2.3 Evaluation of Licensee's Report 2

3.

GENERAL INFORMATION...............................................

2 3.1 Identification of Class IE Electrical Systems...............

2 3.2 Service Conditions 3

3.3 Qualification Documentation.

4 4.

EQUIPMENT DATE REVIEW.............................................

4 4.1 Qualified Equipment 4

4.2 Equipment With Aging Less Than Plant Life..................

4 4.3 Equipment to be Replaced, Modified, or Relocated - Licensee Identified...........................................

4 4.4 Equipment with Unresolved Qualification Items 4

4.5 Equipment Not Qualified....................................

5 4.6 Outstanding Items - Licensee Identified....................

5 4.7 Discussion of On-Site Inspection...........................

5 5.

CONCLUSIONS.......................................................

5 Review Tabulation Sheets Used in Evaluation of Licensee's Report List of Standard Systems List of Documents That Support Environmental Qualifica-tion of Licensee's Equipment Outstanding Items (Licensee Identified)

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INTROD1.'CTION 1.1 General T!.2

'7 5ffice

-f ingecti;.. ' 2 r.f c : : nc... (IfE;.: sue l Ba'. ? c t in 79-01B, " Environmental 0"alification of Class IE Equipment" in January 19S0.

This bulletin required the licensee to perform a detailed evaluation of tha environmental qualification on Class IE electrical equipment required to function under postulated accident conditions and to submit a report on this action.

This document is a report on the evaluation of the licensee's response to this bulletin.

2.

BACKGROUND AND DISCUSSION 2.1 General i

i The evaluation of the 1.censee's resper.se was accomplished by examining l

l the licensee's report for completeness and technical accuracy. The licensee's report used in this evaluation is dated November 12, 1980, and includes the responses to the Bulletin Supplements with the exception of I/E Supplement No. 3 issued on October 24, 1980.

.. ~

4 5

i 2.2 On-Site Inspections l

Cc ope n er.ts ta t s '.1 : e exc.irxJ di. ring *

.ield inspection sdeduled for the first part of r)ecamber will be identifid in Revision 1 to the TER.

i 2.3 Evaluation of Licensee's Report i

Each component as addressed on the Component Evaluation Work Sheets (CES) of the licensee's report was examined for completeness and accuracy to the criteria given in the bulletin.

This examination assumed qualification documents (analysis, test reports, etc.) referenced by the licensee in their submittal are acceptable.

The results of this examination are documented in Attachment 1.

The CES page numbers in column 1 of Attachment 1 is the same CES page found in the licensee's report.

3.

GENERAL INFORMATION 1

i 3.1 Identification Of Class IE Electrical Equipment The licensee's list of systems was compared to the systems listed on.

This list is considered to be a standard list for pressurized water reactors.

, _... _. - -.. _ - _. - - - _., _ _. _ _ _. ~ -. -

. It is recognized that there are differences in nomenclature of systems because of plant vintage and engineering design, therefore, many of these syste'ns may not exist f t r Farley Unit I plant cr the function of these systems for the Farley Unit I plant may be performed by comparable systems with driterent names. In any case, all the systems of Attach-ment 2 were not addressed or listed in the licensee's report. To insure completeness and uniformity of reports of similar design, it is considered that the licensee shculd address the following systems:

(1) Steam Dump (2) Containment Sump.

Each of the above systems should be analyzed and a brief discussion should explain how the system was addressed or why it was excluded from the report. For example: " Reactor Protection System - This is a valid system designation at Farley Unit 1 plant; however. the input signals to this system are obtained from various components in other systems that are included in this report."

3.2 Service Conditions The service condition accident environment, IELB/LOCA inside contain-ment and IELB outside containment :4re indicated or discussed in the licensee's report.

l

. 3.3 Qualification Documentation is a list of documents (test reports. aralysis. letters,

.) used by the licensee in determining the environmental qualifica-e:

Lawn of plant equipment for Farley Unit 1.

Inese reierences have been tabulated by the licensee and are indicated on the applicable CES of their report.

4.

EQUIPMENT DATA REVIEW 4.1 Equipment that is considered to meet IEB 79-01B requirements are categorized as 1 in the last column of Attachment 1.

4.2 Equipment whose qualified life (Aging) is less than the life of the plant is categarized as 2 in the last column of Attachment 1.

l 4.3 The licensee has identified specific equipment which has been or is being replaced, modified or relocated as a result of their IEB 79-01B efrorts. This equipment is categorized as 3 in the last column or.

4.4. Equipment whose qualification is unresolved (such as, a qualification record search is still in process, tests are scheduled to determine qualification, additional information is needed by the NRC reviewer to satisfy him that equipment is qualified, etc.) is categorized as 4 in the last column of Attacament 1.

I 1

. 4.5 Equipment that the licensee has identified as not being qualified required an LER with justification for continued plant operation.

4 No LER's were received in Region II for Farley 1.

4.6 Equipment whose qualification (Aging exempted to a certain degree -

see DOR guideline Section 4) is unresolved, as identified by the licensee is listed in Attachment 4 as Outstanding Items.

The licensee has provided justification for continued plant operation for many, if not all, of these outstanding items in their report. In many cases, this is provided on their CES or in a special section of the report. In some cases the licensee states that this justification is by Engineering Analysis that are available at their office.

4.7 A discussion of the equipment examined during the onsite inspection will be addressed in Revision 1.

5.

CONCLUSIONS Due to the time constraints imposed by the Commission Memo and Order of 5/23/80 this evaluation is based on the licensee submittal dated November 12, 1980. This licensee's report does not address all items that may be pertinent to Farley Unit 1 plant as a result of IEB 79-01B Bulletin Supplements 2 and 3 issued on 9/30/80 and 10/24/80, respectively. Specifically, information on cold shutdown and TMI Lessons Learned related equipment which is received subsequent to 11/1/80 will be evaluated by EQB of NRR.

6-l The licenssee's actions meet the requirements of the Commission Memo and 1

Order or 5/23/80 and justification for cantinued plant operation with many j

of the components that have unresolved qualification items is indicated in Section 4.c.

Based on the information available, the Region 11 reviewer cc: d ?ers that 'he justificat ica i, c..:en.surate f cr the areas identifica, that the proposed corrective action meets requirements of the Commission j

Mecio and Order of 5/23/30, and therefore, plant operation can continue until these items are resolved as committed to by the licensee.

This evaluation is based on the information supplied by the licensee in their 1

i submittal, their FSAR, and the assumption that the Qualification Documents

]

(Test Reports, Analysis, Letter, etc.) are acceptable.

The results of this evaluation does not necessarily imply that the equipment l

l is unreliable, unsafe or represents a significant safety issue; it doas I

imply that additional information is required. This is indicated by the i

applicable categorization irlicated in the last column of Attachment 1.

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- ur N = In.II. cu the item .a teot Appittable a) lesting schedule but not complete j , UL = ladit.. i c e the i t e n. 6, tluremolved. Licensee identified b) Reviewer needs additional information P = Paupil.tary c) yu.el. Hecord search et t!! in procese L = l.icenure identliled 5 = t.quipment not qualilled M = Heviewes identifical 6

• It em islent if ied to 1,QB for resolution

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o ATTACHMENT 2 FUNCTIONS / SYSTEMS LIST (W) PWR w a F. "itiu..on er ce n ;.u.ces of LUCA Or MSLB 1. Reactor Protection 2. Safeguards Actuation 3. Containment Isolation 4 Main and Auxiliary Steam Isolation 5. Main and Auxiliary Feedwater Isolation 6. Feedwater Control 4 7. Containment Spray 8. Containment Air Purification / Cleanup 9. Containment Ventilation / Cooling 10. Containment Combustible Gas Control 11. High Pressure Injection 12. Low Pressure Injection 13. Accumulators 14. Residual Heat Removal 15. Chemical and Volume Control 16. Pressurizer Spray 17. Power Operated Relief Valves 18. Steam Dump 19. Containment Radiation / Monitoring 20. Containment Radiation / Sampling 21. Component Cooling Water 22. Service Water I 23. Emergency Power 24. Containment Sump 25. Control Room Habitability 26. Safety Equipment Area Ventilation 27. Auxiliary Feedwater 28. Rea: tor Coolant m, r-.m. _-,e ._.y..,, - -. -,, ----,,7, c,,--

AIIACRME.NI. LIST OF DOCUMENTS THAT SUPPORT ENVIRONMENTAL QUALIFICATION OF L: :?: = ' ' S =Q m ': T f 1. WCAP 9157 - Environmental Qualification of Safety-Related Class IE Process Instrumentation (Westinghouse Proprietary - Class 2) and Westinghouse letter APW-A-5141 dated February 14, 1980. 2. Wyle Laboratories SI.Q Test Report 44354-1 dated March 8, 1979. 3. General Electric Company Report -Low Voltage Elect rical Containment Penetration Qualification Test Report. 4. Boston Insula *.ed Wire and Cable Company Test Report 73E062 dated September 7, 1973 and Test Report 74A023 dated January 24, 1974. 5. Westinghouse letter APW-A-5141 dated February 14, 1980 and Westinghouse letter NS-TMA-2154, Andersoa to Stoltz (Test)(Westinghouse Proprietary - Class 2). 6. Automatic Switch Company Test Report AQS 21678/TR. 7. Acme - Cleveland Development Company Qu,lification Report for NAMCO Controls Limit Switch Model EA-180 dated November 21, 1977. 8. WCAF 8541 -Topical Report -Seismic and Environmental Testing of Foxboro Transmitters (Westinghouse Proprietary Class 2) and Westinghouse letter APb-A-5141 dated February 14, 1980. 9. '.he Okonite Company Engineering Report No. 141 dated February 29, 1972 and Report 143 dated March 20, 1972. 10. Wyle Laboratories Test Plan 5e5/0359/ES for Lesel Transmitters for Delaval/ Gems Sensor Division. dated October 6, 1978. 11. Limitorque Corporation Test R.eport 600456 dated December 9, 1975. 12. Joy Manufacturing Company Qualification Test Report X-604 for Containment Coolers. 13. WCAP 7820 with Supplements 1 through 4, and Westinghouse letter to SCSI (O. Batum) dated February 14, 1980 for Electric Hydrogen Recombiners. 14. Limitorque Corporation Technical Report No. F-C3441 dated September 1972. 15. Limitorque Corporation Technical Report No. F-C2232-o; dated November 1068. 16. Franklin Institute Research Laboratory Test Report F-C3834 dated March 1974. l ~ ~.. _

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4 4 im ee ev p fE Facility: Farley 1 Docket No. : 50-348-NOTES: i 7. This component is to be replace:1 with one having full environmental i qualification documentation by the end of the third refueling outage. 2. The licensee has determined the qualified life for this component to be in excess of 40 years based on weak link activation energy and Arrhenius model. Manufacturer's confirmation has been requested via Bechtel letter V-3818 dated 6/5/80. CODE: Lt. Sw/LS... Limit Switch SV.......... Solenoid Valve S.. ..... Switch (Level S'a', PS - Pressure SW, FS - Flow SW) PT/LT. Pressure or Level Transmitter MOV..........fotor Operated Valve Mtr......... Motor C........... Controller TE/RTD...... Temperature Element / Resistance Temperature Detector RL.......... Radiation Detector TB/JB....... Terminal Block / Junction Box .-_}}