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\ 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 Office has identified two cases in which the Franklin Technical Evaivation appears to be based on outdated or incorrect information.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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