ML20126M904

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Identifies Two Cases in Which Franklin Research Technical Evaluation Rept Re TMI-1,App J Review,Appears to Be Based on Outdated or Incorrect Info
ML20126M904
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 08/11/1981
From: Jordan E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: Novak T
Office of Nuclear Reactor Regulation
Shared Package
ML20125B444 List: ... further results
References
FOIA-96-207 NUDOCS 8108270589
Download: ML20126M904 (7)


Text

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i

\ UMTED STATES bM i  ! NUCLEAR REGULATORY COMMISSION

7, p! wAsem.ovow. o.c. noses Docket No. 50-289 AUG I I l98i i

! MEMORANDUM FOR: T. Novak. Assistant Director for Operating Reactors.

! Division of Licensing. NRR

! FROM: E. Jorden. Deputy Director. Division of Resident and

{ Regional Reactor Inspection. IE B

SUBJECT:

TMI #1 APPENDIX J REVIEW Amendment No. 63 to the Three Mile Island Unit 1 (TMI #1) Technical Specift-cations, issued March 30, 1981, made changes relating to primary containment l 1eakage testing. The Safety Evaluation Report in support of Amendment No. 63 l references the Technical Evaluation Report done by Franklin Research Center i dated July 3,1980. In the review of the leakage rate testing program at TMI fl. the Region ! Office has identified two cases in which the Franklin Technical Evaivation appears to be based on outdated or incorrect information.

l 2

The Franklin Technical Evaluation Report states that the i nuclear service closed cycle cooling water system (MSCCCW) "is a closed

! system inside contalmnent and is not liable to rupture post-accident.

Appendix J does not require that these valves be tested." However. Amend-l ment No. 61 to the Technical Specifications issued January 26, 1981, removed l 36 snubbers in portions of the NSCCCW system inside containment of which

! valve MS-V11 is a part (Enclosure 1 and 2). The snubbers were removed because I this system was not considered to be safety-related. Since the NSCCCW system is no longer considered safety-related and the snubbers are no longer inspected, we conclude that this system may not remain intact under post-accident con-ditions. Therefore, valve NS-V11 should be subject to Type C leakage rate We note that the other containment isolation valves in the NSCCCW testing system (.NS-V4 V15 and V35A) are fluid blocked by a seal unter system or are

being Type C tested. Valve NS-Y11 is the only containment isolation valve in l the NSCCCW system not fluid blocked or testad.

l l The Franklin Technical Evaluation Report also states that valves IC-V16 and l

IC-V18 in the intermediate cooling system are "in a closed system inside con-( tainment which is designed to remain operational throughout the post-accident period and is not 11ab .e to rupture as a result of a LOCA. Appendix J does

! not restre that these valves be tested." The ton 1 Office has reviewed

' the Intermediate Cooling System Drawing No. 302- (Enclosure 3) which appears

! to inTIcate that this system has been designed primarily as Seismic Class II.

l Seismic Class !! structures, components, and systems as defined in the FtAR f

! CONTACT: H . J. Wo ng . ![ ./

j 49-24767 j

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T. Novak AUG 11 1981 have been designed "in accordance with procedures of the Uniform Building Code." Therefore it does not appear that this system will remain intact under post-accident (seismic) conditions. Standard Review Plan Section 6.2.4 states that in order to qualify as a closed system inside containment, the closed system must be designed to be seismic Category I. We note that the other containeent isolation valves in this system (IC-V4 V6, V3 V2) are fluid blocked by a seal unter systen or are Type C tested.

We have had several discussions with J. Aspaker and p. Hearn Contalmeent Systems Branch, regarding these two systems and the Appendix J review in general. We request that the nuclear service closed cycle cooling unter system Cvalve NS-Vil) and the intermediate cooling systes (valves IC-Y16 and V18) be reviewed in light of the cassents provided in this memorandum.

It appears that these valves should be incloded in the Type C testing program. If you have additional spestions, please contact this office. ,,

^

tY' Edush . Jordan. Deputy Director Divisi n of Resident and Regional Reactor Inspection Offits of Inspection and Enforcement

Enclosures:

P & ID's (RSCCOf and Intermediate Cooling) cc: J. Sniezek. IE D. Eisenhut. NRR L. Rubenstein. NRR W. Butler. NRR J. Shapaker. NRR P. Hearn. NRR E. Brunner. RI W. Rekito. R!

R. Baer. IE R. Woodruff. IE H. Wong. IE

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