ML19241B686
| ML19241B686 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/11/1979 |
| From: | Gilleland J TENNESSEE VALLEY AUTHORITY |
| To: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 7907230056 | |
| Download: ML19241B686 (10) | |
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TENNESSEE VALLEY AUTHORITY CHATTANOOGA, TENNESSEE 500C Chestnut Street Tower II 2.11 G79 7 9 J UN 13 A6 33 Mr. Nonr.an C. Nseley, Dire ; tor Division of Reactor Operations Inspection Of fice of Inspection and Enforcement U.S. Nuclear Regulatory Cocr.ission Washington, DC 20555
Dear Mr. Moseley:
OFFICE OF INSPECTION AND ENFORCEMENT BULLETIN 79 RII:JPO 50-259, -260, -296 - BROWSS PERRY NUCLEAR PLANT UNITS 1, 2, AND 3 It response to J. P. O'Reilly's February 8,1979, letter which transmitted IE Bulletin 79-01, we are enclosing a final report outlining the results of our investigations at Browns Ferry.
Very truly yours, J. E. Gillele.nd Assistant Manager of Power Faclosure
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Mr. James P. O'Reilly, Director (Enclosure)y Office of Inspection and Enforcement U.S. Nuclear Regulatory Comission Region II - Suite 3100 101 Marietta Street Atlarra, deorgia 30303 g g.7 p
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ENCLOSURE RESPONSE TO IE BULLETIN 79-01 FOR BROWSS FERRY NUCLEAR FLANI TVA has surveyed the electrical equipment installed at Browns Ferry Nuclear Plant inside primary containment that is required to function under accident conditions, and examined the docucentation for its environ = ental qualification. Specific equipment ite=s are listed followed Also attached by a reference to the appropriate qualification documents.
are data sheets giving the co=ponent description, description of the the environment to which the component is qualified, accident environment, The fo11 ovine contains the results test method, and reference docu=ent.
of our survey.
Iten 1 - Connectors Culton and Acphenol electrical conaectors associated with units 1 and 2 have been qualified for a 10-year life in accordance with Wyle Laboratories test report No. 43854-1 dated March 23, 1978.
Bendix connectors associated with unit 3 have been qualified for a 10-year 44107-1 dated life in accordance with Wyle Laboratories test report No.
Septe=ber 19, 1978.
Ite= 2 - Penetrations Test reports fro = the Physical Science Physical Science Corporation:
Corporation dated May 4,1970, (test report No.18312) show dielectric and leak tests were successfully performed at a te=perature of 310 degrees The manufacturer has stated that Fahrenheit and a pressure of 60 psig.
the penetration will successf ully operate at temperatures of up to It should also be noted that tests were conducted 400 degrees Fahrenheit.
43854-1 dated March 23, 1978) on by Wyle Laborateries (test report No.
electrical connectors with several connectors attached to a Physical The two test reports supply suf ficient qualification Science penetration.
data f or the Physical Science penetrations. These penetrations are used in units 1 and 2.
(CE) Series 100: CE Series 100 penetrations have Cencral Electric Corpany been qualified in accordance with CE Lov Voltage Qualification Test Report No. 74-502-3 dated September 1973 and Lov Voltage Qualification Test Report Addendu= No. 1 dated March 1974. These penetratiens have been used as replacement penetrations on unit s 1 and 2.
CE cannister-type penetrations have been qualified CE Cannister-Type:
in accordance with CE Prototype Testing Qualification Reports ETAQ-007 16, 1970. These
-003, -009, -046, -055. -056
-057, and -061 dated March penetrations are used on unit 3.
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. Item 3 - Tercinal Blocks i
There.are no unprotected terminal blocks used on the Browns Ferry units (see response to which must function in a post-accident environnent13, 1978, J. E. C111 eland IE Bulletin 78-02 for Browns Ferry dated February to J. P. O'Reilly).
It en 4 - Limit Switches installed The subject limit svitches referenced in IE Circular 78-08 were not in any contain=ent at Browns Ferry (see response to IE Bulletin 78-04 for 23, 1978, J. E. G111 eland to J. P. O'Reilly).
Browns Ferry dated March Notifi-IE Bulletin 79-01 expanded the list of unqualified limit switches.
23, 1979, cation to the Nuclear Regulatory Coanission (NRC) was cade on February inforcing the NRC of the use of a Namco model SL3-E2W (prescnt model EA-700) limit switch on the inboard main stea= isolation valves at Browns Ferry.
NRC was also notified on April 10, 1979, of the use of a Namco model SL2-c11 limit svitch on a testable check valve in the core spray system at Browns In both cases it was concluded that environmental qualification Ferry.
No other licit switches which are of the subject switches is unnecessary.
required to function under accident conditions have been found in the con-tainment area at Browns Ferry.
Item 5 - Cable Splices associated with electrical penetration assemblies Electrical cable splice CE dated June 26, 1978.
were confirmed to be qualified in correspondence fro:
These splices were qualified during the tests conducted by CE on the cannister-type and Series 100 penetrations.
Electrical cable splice asse=blies were also qualified in accordance with 43854-3 dated April 26, 1978.
Wyle Laboratories test report No.
I t e= 6 - C abl et in the contain:ent areas There are four types of cables used on equipment They are TVA-types CPJ and CPJJ, CE-type Vulkene, and at Browns Ferry.
The Wyle Laboratories test on the electrical cable ITT-type Surprenant.
43854-3 dated April 26, 1976) con-splices asse:blies (test report No.
No cable tained splices using cables of the Vulkene, CPJ, and CPJJ types.
We consider this sufficient f ailures were reported during this test.
qualification.
The ITT cable has been qualified in accordance with Isoredix Test Report No. 375-02 dated March 1975.
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, In addition to the above tests, cable sa=ples were installed in each units' containment to study the long-range ef f ects of radiation and te=perature on these cables. The installation dates were as follows.
Unit 1 - Dece=ber 12, 1978 Unit 2 - June 1, 1978 Unit 3 - October 1978 These cables will be sa= pled periodically to determine the rate of cable deterioration from the effects of radiation and temperature.
Ite= 7 - Primary Containcent Hydrogen Sensor The primary containment hydrogen sensor has been qualified in accordance with CE test report (CE 1RT-QTR-063) dated March 12, 1976.
Item 8 - Limitorque Valve Operators The following test reports provide qualification of the Limitorque valve operators.
1.
franklin Institute Research Laboratories Test Report No. F-C2232-01 dated November 1968.
2.
Limitorque Coc:pany Test Laboratory Limitorque Valve actuators for Pk'R Service / Project No. 600456, dated June 7,1974, thror;;h Nove=ber 22, 1974.
3.
Limitorque Valve Control Test Report January 2,1969. Engineering Order No. 600198.
4.
Lockheed Electronics Company Test Report No. 2120-4594 dated July 31, 1968.
Iten 9 - Valv'e Motora Notification was made to NRC on March 13, 1979, informing NRC of the use of Class B motor vinding insulation on two motor-operated valves located in the containment area. These valves are FCV-1-55 (Main Steam Line Drain) and FCV-74-78 (RHR Head Spray). These valve motors are to be rewound using wire with a Class H insulation rating during the next refueling outage of each unit. As of this date, this work has been completed on unit 2, with plans to cocplete this work on units 1 and 3 this fall.
It en 10 - Target Rock Relief Valve s (Three-stage, codel 67F)
The ASCO solenoid valves (ASCO Cat. No. kTHTX 8300 E6ST) used on ADS relief valves has been genlified in accordance with Plant Equipnent Design Engineering N eorandu: No. 126-62, dated January 15, 1975.
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4 Iten 11_- Target Rock Relief Valves (Two-Stage model 756F ADS valves for units 1 and 2)
The solenoid (Trombetta model No.1/2 SP.5-A-01) on the replaceeent Target Rock relief valves used for ADS on unita 1 and 2 has been qualified in 21, 1977, accordance with Target Rock Test Procedure No. 2063C dated February and Qualification Report No. 2199A dated January 9, 1979.
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REFERENCE DOCUMENTS a
1.
Wyle Laboratories Report 43854-1 dated March 23, 1978 2.
Wyle Laboratories Report 44107-1 dated September 19, 1978 3.
General Electric Report 74-502-3 4.
General Electric Report EPAQ-007 5.
General Electric Report EPAQ-008 6.
General Electric Report EPAQ-009 7.
General Electric Report EPAQ-046 8.
General Electric Report EPAQ-055 9.
General Electric Report EPAQ-056 10.
General Electric Report EPAQ-057 11.
General Electric Report EPAQ-061 12.
Wyle Laboratories Report 43854-3 dated April 26, 1978
- 13. General Electric Report IRT-QTR-063 dated March 12, 1976 14.
Franklin Institute Research Laboratories Test Report T-C2232-01
- 15. Plant Equipment Design Engineering Hemorandus No.126-62
- 16. Target Rock Report 2199A dated January 9, 1979
- 17. Limitorque Corporation Test Laborazories Project 600456 18.
Isoced)x Report 375-02 dated March 1975 56EE56
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