ML19347B647

LER 80-017/01T-0:on 800923,during Review,Per IE Bulletin 79-01b,documentation to Demonstrate That Breaks on Motor Operators on Purge Valves AH-V1B/C & safety-related Valves DH-V5A/B Re Environ Qualified Found Insufficient

ML19347B647
Person / Time
Site:	Three Mile Island
Issue date:	10/08/1980
From:	Mitchell D METROPOLITAN EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19347B648	List: ML19347B647
References
IEB-79-01B, IEB-79-1B, LER-80-017-01T, LER-80-17-1T, NUDOCS 8010150492
Download: ML19347B647 (3)

Text

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TLL 524 7 U S. NUCLEA"1 f.E ULATC%.Y ConsMiss ON (d aunc Poets 384 mm LICENSEE EVENT REPORT iPt.E44E aunt em TYPE ALL REQUIRED INFORMATIONI CoNTRob sLocx: 11 i

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Ioe4 i  ! motor coerators on ource valves AH-VlB/C and safety related valves DH-V4A/E and i e i 5 ! l DM-VS A/B are environmentally cualified. The unit is in a cold shutdown condition i I

IJ46) land the redundant urge valves outside containrent are fully cualified, b.3 I Iosa!I 50 7 8 9 COM8 vatvt SysTru cAust CAU5f Sb8C00E COM*cN ENT 000E $LaCOCE COCE 003E $U8 CODE l0191

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CAUSE CESCRIPTICN AND OCARECTIVE ACTIONS h to meet i l !o!iThe cualification tests for the ourse valve operators were insufficient W lthe desien rec.drements. The cricinal desien recuimments for the DMR valves did !

Corrective I I , 2 ! I not assume sienificant radiation exoosure to the valve operators.

i ' ! s i l action will be to establish that the brakes are cualified.

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TLL 524 NARRATIVE REPORT TMI-l i LER 80-17 EVENT DESCRIPTION AND PROBABLE CONSEOUENCES It has been deter =ined that there is insufficient documentation to demonstrate that the brakes on the motor operators for purge valves AH-V13 and AH-VlC are environmentally qualified. Documented evidence is not available to show that the brake is qualified for the radiation condi: ions assumed in accordance with Bulletin 79-013.

The FSAR indicates that electric motor valve operators located inside the reactor building are designed to withstand potential effects of radiation.

Since documentation for the brake is unavailable, this condition is report-able in accordance with 79-013 Supplemental Information me=o and Technical Specification 6.9.2A(9).

In addition, safety related valves DH-ViA, DH-V45, DH-V5A, and DH-V5B located outside containment have brakes that lack docu=entation to verify that they are qualified for the post accident radiation exposure assumed in accordance with Bulletin 79-01E.

Unit I was in cold shutdown when the lack of documentation was discovered.

There is no indication at this time tha: the brake should be expected to f ail prior to the valve performing its intended function.

The redundant purge valve ind operator ou: side containment are fully qualified in accorda; :e with IEB 79-013.

CAUSE DESCRIPTION AND CORRECTIVE ACTION The qualification tests for the purge valve operators were insufficient Oc meet the design requirements.

The original design requirements for the Decay Heat Removal valves did not assume significant radiation exposure to the valve operators and, therefore, radiation qualification was not a requirement.

No i==ediate corrective action is required. Long-tern ccrrective action will be to establish that the brakes are qualified for the expected conditions or to replace the unqualified components.

The schedule for completion of the corrective action is the end of the first refueling after restart. This schedule is justified because valve operation will be completed prior to the accumulated exposure exceeding 104 Rads.

The purge valves exposure during power ope.ation is approximately 10=r/t.: and total operation = "--il the end of cycle 5 will be less than 51 x 103 hours0.00119 days <br />0.0286 hours <br />1.703042e-4 weeks <br />3.91915e-5 months <br />.

The purge valves close on a reactor trip and closing time is 5 seconds.

Potential acciden: exposure prior to closure would be negligible.

The decay heat removal valves are located outside containment. Post acciden:

high radiation doses would not be experienced until the Low Pressure Injec: ion pumps have been placed on recircula: ion to the reactor building sump. The

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i l' Narrativa Report TLL 524 LER 80-17 )

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4 i affected valves have completed their intended function when the transfer to i the sump is complete.

r AH-Vl3 (C) Limitorque Corporation SMB-2 Order No. 339470A, Serial No. 109015

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DH-V4A (B) Limitorque Corporation SMB-0 Order No. 336584C, Serial No. 103509 I

DH-VSA (B) Limitorque Corporation SMB-0 Order No. 341174D, Serial Sos. 105902, 105903 i

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