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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 | |||
{ | |||
Regional Reactor Inspection. IE B | |||
==SUBJECT:== | ==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 | 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 | |||
The Franklin Technical Evaluation Report states that the i | references the Technical Evaluation Report done by Franklin Research Center i | ||
dated July 3,1980. | |||
Appendix J does not require that these valves be tested." However. Amend- | 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Technical Evaivation appears to be based on outdated or incorrect information.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 | |||
l l | i nuclear service closed cycle cooling water system (MSCCCW) "is a closed system inside contalmnent and is not liable to rupture post-accident. | ||
IC-V18 in the intermediate cooling system are "in a closed system inside con-( | 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 l | ||
The Franklin Technical Evaluation Report also states that valves IC-V16 and l | |||
j | 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 | |||
/ | |||
l' | l' | ||
/ | |||
l | l 91os m os si x4 4 | ||
91os m os si x4 | |||
T. Novak | 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. | 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. ,, | 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:== | ==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! | 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 | R. Baer. IE R. Woodruff. IE H. Wong. IE | ||
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==REFERENCES:== | ==REFERENCES:== | ||
16 Il | 16 Il | ||
/0 C F4 S'O.f4 Co) b a,,' | |||
ACTION OFFIG (STABUSHED CouPLETiOH DATI | k' wun u t t-n 1 72) | ||
PitSON A5 SIGNED 1 | ACTION OFFIG (STABUSHED CouPLETiOH DATI catt PitSON A5 SIGNED 1 | ||
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.i i- | .i CLOSEOUT METHOD i- | ||
'f W k o d To G H j y n s a d' <rh de n i uowy/ok',, | |||
Wir/?s C Ah o ne e nil 4/e ir, A>na M redew.) | |||
ir, A>na M redew.) | l daft to | ||
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1 10 St SENT TO RECilVING OfflCE AND | < - <.. ~. | ||
u-rn~> | |||
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: e.... s | |||
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1 10 St SENT TO RECilVING OfflCE AND retvious IDitoN5 08 1M!S PO'* | |||
Att oe50ttit AND tsiltiNG 510 Cal Sm0VLD St RETURNED TO INiflATING OfflCE UPON COMPLific Nec 'Otw Se l | |||
3n | |||
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Latest revision as of 17:51, 12 December 2024
Text
.
i bM
\\
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
{
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. ![
./
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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