ML19294A783

Responds to IE Bulletin 79-01.Forwards Ltr Re Results of Architect/Engineer Insp of Reactor Containment Which Recommended That Several Terminal Blocks Be Replaced.These Blocks Were Replaced

ML19294A783
Person / Time
Site:	FitzPatrick
Issue date:	03/01/1979
From:	Leonard J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
JAFP-79-105, NUDOCS 7903220135
Download: ML19294A783 (6)

Text

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. POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITzPATmcx NUCLEAR POWER PLANT JOHN o. LEONARD, JR.

Resident Manager S P.o. BOX 41 Lycoming. New York 13093 31s.35384o March 1, 1979 JAFP-79-105 Mr. Boyce H. Grier, Di rector United States Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

SUBJECT:

NRC I & E BULLETIN 79-01

Dear Mr. Grier:

The staff at the James A. FitzPatrick Nuclear Power Plant has reviewed the ret?nt Bulletin issued by your office on February 8, 1979, ie.Bulletin 79-01. In addition, we have discussed this Bulletin with the Nuclear Operations Section of our Headquarters Office.

During this effort, we have reviewed our responses to I & E Bulletins 77-05,77-05A, 77-06, 78-02, 78-04, and I & E Circular 78-08. It is our belief that in these responses we have forwarded to you the information which apparently some licensees have been unable to provide. Specifically with regard to Bulletin 78-04 concerning limit switches, the report of our review informed the regulatory staff that we indeed have similar limit switches which are now discussed in Bulletin 79-01, although this information had not been requested at that time. Our review in conjunction with our nuclear steam supply system vendor indicated that these limit switches in their present use, are not required to perform a safety-related function in a LOCA environment and this was so reported.

In addition, af ter discussion with your staff in October, as set forth in my letter of October 3, 1978 to Mr. Ebe C. McCabe, we committed to making a physical inspection of the electrical installation in our reactor containment during the refueling outage that was completed during the end of November 1978. This inspection was made by representatives of our architect engineer in order to fulfill our commitment to your staff and the results of this inspection discussed with your reactor inspector. The report was made available for the inspector's review.

This report recommended that several terminal blocks be replaced because qualification was not readily discernible for them although qualification may be satisfactory. These blocks were replaced.

A copy of the basic letter forwarding the results of the architect engineer's inspection of the reactor containment is attached for your staffs review. Additionally, qualification data which we have on site 7903220/3f

Mr. Boyce H. Grier, Director March 1, 1979 United States Nuclear Regulatory Commission JAFP-79-105 Page

SUBJECT:

NRC I & E BULLETIN 79-01 has been reviewed by two of your inspectors. Other qualification data which is in the files of General Electric Company's Nuclear Engineering Division, San Jose, California is available for further review and discussion directly with our nuclear supply system vendor should this be required.

We believe that our prompt action in these matters has fulfilled the requirements set forth in your recent Bulletin 79-01. If however, all the information presented to date is not sufficient, please inform us of any further information which should be forwarded to your office or the Office of the Dircrtor, Division of Reactor Operations inspection, Office of Inspection and Enforcement, Nuclear Regulatory Conunission, Washington, D. C. 20555

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Very troly yours,,

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JDL:brp v[JOHN LED. tCD ARD, JR.

87@tBA l 9 Enclosure RESIDENT MANAGER CC: G. T. Berry, PASNY, NYO ,

G. A. Wilverding, PASNY, NYO, P. W. Lyon, PASNY, NY0 M. C. Cosgrove, JAF Y

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R. J. Pasternak, JAF Document Control Center

03S 106 STONE C5 WEBSTER ENGINEERING CORPORATION 245 SUMMER STREET. BOSTON. M ASSACH U SETTS ADDRESS ALL CORRESPONDENCE TO P.O. BOX 2325. BOSTON. MASS. 02107 on st c usTRucTiom

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Mr. J. D. Leonard, Jr. November 3,1978 Resident Manager James A. Fit: Patrick Nuclear Power -Plant . w L 0..No. 12966 .'

Power Authority of the State of New York m q_m A P.O. Box 1.1 Lyco % g, NY 13093 RECEIVED

Dear Sir:

NOV 61S/e I & E CIRCULAR 78-08 POWER AUTHORITY

. TASK 12966.08 - 00022 J. A. F. PLANT JAMES A. FITZPATRICK NUCLEAR POWER PLANT On Cetober 11, 1978, Stone & Webster was authori::ed to perform two tasks outlined in Power Authority's letter to NRC, dated October 3, 1978; subject:

I & E Bulletin 78-08 Tnese tasks are described as follows:

Task 1 - Research the documentation and physically inspect the dry well for other splices (other than penetrations) involving safety-related equipnent and, if found, determine their environmental qualification. Tnis activity is to be co=pleted prior to the co=pletion of the present refueling outage.

Task 2 - Inspect a representative sample of safety-related electrical equipment, including terminal blocks within the dry well, to ensure its confornance to design requirements. This inspection and resolution of any nonconformance found should be co=pleted prior to January 1,1979.

Seone of Work The scope of these tasks includsithe following work:

1. Identify all QA Category I cables and electrical equipment located in the dry well that are required to operato during the design basis accident.

2. Identify the location of splices which are specified on the drawings for Category I safety-related cables within the dry well.

CL S w PA pas- 24 7%

JDL,Jr. 2 038 107

3. Detemine the environmental qualifications of the splices identified in 2.

4. Perform field inspection on October 17-20 of a representative sample of safety-related electrical equipment, including teminal blocks, to ensure its conformance to design requirements.

5. Review FQC documentation for verification of electrical equip =ent installation based upon the design requirements. -

6. Present the findings from the field inspection.

7. Prepare a letter report on the above tasks.

_ Documentation The following documentation was reviewed to acco plish the Scope of Work:

Drawings / Reports 11825- % 46I - Conduit Plan - Reactor Building n 825- G 46Y - Conduit Details - Reactor Building n825-FE-46Z - Cenduit Plan - Reactor Building _

n825-FE-46AA - Conduit Plan - Reactor Building n825-BM-46I -Em of Fatorial ll825-EM-46Y - Bill of Material

. 11825-BM-46Z - Bin of Material 11825- E 36G - 575/120 V Power - I 104D JB0 + 1 n825-FE-36H - 575/120 V Power - I 104B JB0 + 1 11825- L 36Q - Control and Indication - I 101B JB1 H 825-FE-36S - Control and Indication - I 100F JB1 11825-FE-36U - Control and Indication - I mn JB1 -

n825- L 367 - Control and Indication - I 100G JB1 11825- 5 36AB - Inst. Penetration - I 103A JB1 11825- % 36AD - Inst. Penetration - I 103B JB1 n825-FE-3DG - Isol. Vv Relay Cab Chan B .

n825-FE-9FR - 02 I M -043A, 0433, 053A, 053B, 054A, and 54B 11825-E18AY - Wiring Diagram - PCI JB's Sys 02, 16, 20, and 29 n825-E18BK - Wiring Diagram - Misc. PCI Ckts Sys 20 and 29 11825-SE-9ER - 600 V WD 14MOV-005A 11825-SE-9GQ - 600 V WD 10MOV-18 11825-SE-9HC - 600 V WD 10MOV-32 n825-SE-9JJ --600 V WD 12MOV-15 n825-SE-9JU - 600 V WD 13MOV-15 11825-SE-9LJ - 600 V WD 20MOV-82 n825-SE-9LK - 600 V WD 20MOV-94 11825-SE-9LL - 600 V WD 23MOV-15 n825-SE-9LZ - 600 V WD 29MOV-74 Cable Raceway Report EC Cable List Location Equipment List Report EC-0 Installation Instructions for Electrical Penetrations - GEE-34666 Lord /Comstock Procedure 4.3.5 for Cable Tera m tions

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038 108 JDL,Jr. 3 Results of Document Review

1. Cable splices are specified on the electrical drawings at electrical penetrations for QA Category I cables.

2. Procedure for installing cable splices at the electrical penetrations is specified in GE INSTALLATION INSTRUCTIONS GEK-34666. These splices have been qualified by GE to design accident environment.

3. The procedure for verifying the installation of cable splices is described in Lord /Comstock Procedure 4.3.5.

4. No cable splices were specified on the dry well viring diagrams for QA Category I cables at juncticn b-- c :nl? ' .

5. Documentation was not found on the insbilntion procedure for splices at the SOV's or the environmental qualification of the splices. The tapes used in making the splices, Okonite T35 and Okonite T95 have been qualified in Okonite Engineering Report 141. Tne procedure used for the splices included the installation of crimp-type lugs on each cable end, bolting the lugs together, and wrapping the splice with two layers of T95 Okonite tape and one layer of T35 Okonite tape.

This procedure is an accepted method for splices in the~ dry well.

Results of the Drv Well Insoection

1. A sample of splices at electrical penetration X-100F was inspected (cables 1EPSADC061, 1RPSADC069, 1PMR3BC004, 1C1CB30102, and 1HJP3BC070).

The splices were not disassembled. Tne visual inspection indicates that

they were installed based upon the approved procedure. The Lord /

Comstock QA Procedure verified:

a. Proper size and type lug was used

b. Proper tool was used for installing lug

c. Each teminal properly identified and tightened

d. Wires laced or fomed in a neat manner -

e. Shielded wires properly grounded

f. Vire insulation undamaged

g. Correct percanent identification and redundancy

2. Pull boxes (JB-PCI-154, JB-RPS-1A, JB-PCI-1B, and JB-PCI-lC) were inspected to verify that there are no unauthorized splices in pull boxes. No splices were found.

3. The cable splices at the main steam isolation valves were inspected.

The splices were installed based upon the approved precedure.

4. Junction boxes at main steam isolation valves contain Buchannan teminal blocks. Tnese teminal blocks may be qunHfied for the environ-ment but documentation is not available to verify their qualifications.

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JDL,Jr. 4 038 109 Conclusions

1. All splices inspected in the dry well have been installed in accordance with approved procedures and are qualified for their environment.

2. Electrical penetrations are in accordance with the design requirements.

3. The inspection of a representative sample of safety-related electrical equipment within the d:7 well indicates conformance with the design requirements, except for the Euchannan teminal blocks located at the SOV's at the nain steam isolation valves.

Reconnendation _.

Replace Buch nnan tercinal blocks.

The infomation required to replace the Buchannan teminal blocks and asso-ciated junction boxes is shown on attached sketch No. 12966.08 . no002 SK-El.

A copy of the Inspection Report Field Data is attached for your accords.

Ve will be happy to discuss this report with you or any follow-up action required, at your convenience.

Very truly yours, V W L. D. Barnes -

Project Engineer Enclosures RK:MTN O

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