ML17340A761
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UNITED STATES NUCL AR REGULATORY COMMISSION WA~I4I"'I-YON, D. C. 20555
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'b In 1976 Turkey Point Unit 4 developed steam generator tube leaks the denting phenomena.
Unit 4 operated under conditions imposed by until 1978 when the inspection and plugging program was reasonably well established.
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MEMORANDUM TO:
-Yincent Noonan, AD/MQE e$
Q FROM:, 'homas Novak, AD/OR, DL u,
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SUBJECT:
TURKEY POINT PLANT STEAM ='ENERATOR INSPECTIO ~
~egg+tea)gg In 1977 similar license conditions were imposed on Unit 3 when the genera-
'ors on'hat unit began to show denting.
Since Unit 3 denting had not pro-gressed as far as Unit 4 and since the inspection and plugging program had already been established the inspection conditions were imposed by amendment to the license.
Each unit new has steam generators that are plugged between 20 and 25'5 but have not had significant. leakage for two or more years.*
Based on the past experience we find that the inspection procedures, plugging criteria, etc.,
are producing satisfactory results for six month operating periods.
He do not have a technical basis for extending the operating period,
- however, we also do not have a technical basis for continuing to require ou'r approval before returning the units to power operation following a steam genreator inspection.
Therefore, for convenience of the NRC as well as being repre-sentative of the status of the inspection program we propose that the attached revised.license conditions be issued for both units at the Turkey Point Plant.
The attached conditions are modified from the Unit 4 conditions, the most restrictive conditions.
The typed portions are the old. conditions, the handwritten portions 'are new additions.
The main change in the permission to return to power operations upon.:completion of the inspection and safety analysis by the licensee.
Added features ar>> the clear delineation of criteria used for inspection and plugging and the safety analysis by the licensee.
He propose that these conditions be imposed on each unit in March 1981 the next inspection for Unit 3.
Please comment on these conditions by February 23, 1981 Origina1 signed by:
Thomas M..Ifova3g
~'homas Novak, Assistant Director Operating Reactors Division of Licensing cc:
See next page 81022'Fog(G
- The November leak in Unit 3 generator B was attributed to plugs that were loo n
b shocks caused by a faul bypass startup valve.
OFFICE/
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NRC FORM 318 IIO/80)NRCM 0240
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 1
February 10, 1981 A
MEMORANDUM TO:
Vincent Noonan, AD/MQE FROM:
SUBJECT:
Thomas Novak, AD/OR, DL TURKEY POINT PLANT STEAM GENERATOR INSPECTION In 1976 Turkey Point Unit 4 developed steam generator tube leaks due to
.the denting phenomena.
Unit 4 operated under conditions imposed by Order until 1978 when the inspection and plugging program was reasonably well established.
.'n 1977 similar license conditions were 'imposed on Unit 3 when the genera-
.tors on that unit began 'to show denting.
Since Unit 3 denting had not'ro-gr'essed as far as Unit 4 and since the inspection and plugging program had already been established the inspection conditions were imposed by amendment to the license.
Each unit nOw has steam generators that are plugged between 20 and 25K but have not had significant leakage for two or more years.*
Based on the past experience we find that the inspection procedures, plugging criteria, etc.,
are'producing satisfactory results for six month operating periods.
We'do noi have a technical basis for extending the operating period,
- however, we also do not have a technical basis for continuing to require our approval before returning the units to power operation following.a steam generator inspection.
Therefore, for convenience of the NRC as well as being repre-sentative of the status of the inspection program we propose that the attached revised license conditions be issued for both units at the Turkey Point Plant.
The attached conditions are modified from the Unit 4 conditions, the most restrictive conditions.
The typed portions are the old conditions, the handwritten portions are new additions.
The main change is the permission to return to power operations upon completion of the inspection and safety analysis by the licensee.
Added features are the clear delineation of criteria used for inspection and plugging and the safety analysis by the licensee.
We propose that these conditions be imposed on each unit in March 1981 the next inspection for Unit 3.
Please comment on these conditions by February 23, 1981 Thomas Novak, Assistant Director Operating Reactors Division of Licensing
- The November leak in'nit '3 generator B was attributed to plugs that were loosened by shocks caused by a faulty bypass startup valve.
FEB 4 198t 5L GROTEI'HPJ'5 (l)
After operation "
of six equivalent full power months from the be 1
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1 k
11 k
gk old shutdown condition and the steam generators shall nspected unless:
(l ) an inspection of the steam generatorgs is performed within this period
, or (2) an'f
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C continued operation M~~
W~"beyond the authorized period of operation.
Aqy anaPs+s-J continued operation est be submitted at least 45 days pr or to the expiration date of the authorized period of operation-For the purpose of this requirement, equivalent operation is defined as. operation with the reactor coolant at a temperature greater than 350'F.
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(2)
Reactor coolant to secondary leakage through the steam generator tubes shall be 1imited to 0.-3 gpm per steam generator.
With a steam generator tube leakage greater than this limit, the reactor shall be brought to the cold shutdown condition
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within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s~A" inspection shall I
(3) The concentration of radioiodine in the reactor coolant shall be limited to 1.0 microcurie/gram during normal operation and to 30 microcuries/gram during power transients.
.(4) b
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primary to secondary leakage attributable to the denting phenomena is detected in 2 or more tubes during any 2G day perte~~
(5)'he Metal Impact Monitoring'System (NIMS) shall be contained in operation with the capabi lity of detecting losse objects.
If the NIMS is out of service in other than cold shutdown or refueling mode of operation, this fact shall be reported to the NRC.
Arp abnormal indications from the NIMS shall also be reported to the'NRC by telephone by the next working day and by a written evaluation within two weeks.
(6)
Following each startup from below 350'F, core barrel movement shall be evaluated using neutron noise techniques.
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(7)., T
'censee'shall provide for staff review informats ming'the tube'wastage o occur
<during he latter a
') og period whi ch. bcaine-
, Danuary.,
1981" s for 't months of opera ss information is.to be supplied y
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