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UMTED STATES i
NUCLEAR REGULATORY COMMISSION p!
wAsem.ovow. o.c. noses 7,
AUG I I l98i Docket No. 50-289 i
MEMORANDUM FOR:
T. Novak. Assistant Director for Operating Reactors.
Division of Licensing. NRR FROM:
E. Jorden. Deputy Director. Division of Resident and
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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 l
Technical Evaivation appears to be based on outdated or incorrect information.
2 The Franklin Technical Evaluation Report states that the l
i nuclear service closed cycle cooling water system (MSCCCW) "is a closed system inside contalmnent and is not liable to rupture post-accident.
l Appendix J does not require that these valves be tested." However. Amend-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 (.NS-V4 V15 and V35A) are fluid blocked by a seal unter system or are system 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. ![
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j 49-24767 j
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l 91os m os si x4 4
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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