ML17319B325
| ML17319B325 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/14/1982 |
| From: | Hunter R, Hunter R 1 INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.3.1, TASK-2.B.1, TASK-2.B.2, TASK-2.B.3, TASK-2.B.4, TASK-2.D.1, TASK-2.E.1.1, TASK-2.E.1.2, TASK-2.E.4.1, TASK-2.E.4.2, TASK-2.F.1, TASK-2.F.2, TASK-2.K.2.13, TASK-2.K.2.17, TASK-2.K.2.19, TASK-2.K.3.01, TASK-2.K.3.05, TASK-2.K.3.25, TASK-2.K.3.30, TASK-TM AEP:NRC:0678, AEP:NRC:678, GL-82-05, GL-82-5, NUDOCS 8205180515 | |
| Download: ML17319B325 (15) | |
Text
REGULATORY FORMATION DISTRIBUTION 'S EM (RIDS)
AOCESSION NBR:8205180515, DOC ~ DATE: 82/05/14 NOTARIZED: YES FACIL':50>>31'5 Dona'I d G,.
Cook Nuclear Power
'-Pl anti Uni~t ii Indiana
.'50"316 Donald 'G ~
Cook Nuclear Power lPlant~ Unit 2~ -Indiana
'AUTH,NAME" AUTHOR "AFFILIATION HUNTER~R.S.i
'-Indiana K Michigan Electric Co.
~RBC IP ~ NAME RECIPIENT AFF IL'IATION DENTONgH ~ RE Office of Nuclear 'Reactor Regulation~
Di-nector DOCKET 0500031'5 05000316 S UBJECT:
Forwards responses
-to 820317, Generic Ltr, 82 05 ne post TMI r equ) rements for I tems, 1 ~ A ~ 3 ~ 1 p II~ 8 pl II'8 3) II~ 8 ~ 4 p, II', 1' 2tII E ~ 4 ~ 2tII' F ~ 1III~ 8 irII'oD~ itII' E ~ 1'lII' E ~ 4 ~ it II~ F ~ 2 ~ 3i II..K,'2 ~ 13'l, K;2,17 L II~ K ~ 3,1, DISTRIBUTION CODE;-
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-TITLE: Response to NUREG -0737/NUREG 0660 TMI Action 'Plan Rgmts (OL's)
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INDIANA II MICHIGAN ELECTRIC COMPANY P. O.
BOX 10 BOWLING GREEN STATION NEW YORK, N. Y. 10004 May 14, 1982 AEP:NRC:0678 Donald C. Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos. 50-315 and 50-316 License Nos.
DPR-58 and DPR-74 POST-TMI-REQUIREMENTS (GENERIC LETTER NO. 82-05)
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Denton:
This letter and its Attachment respond to Mr. Eisenhut's Generic Letter No. 82-05 dated March 17, 1982.
Very truly yours,
/os
. Hunter Vice President cc:
John E. Dolan Columbus R.
W. Jurgensen W. G. Smith, Jr.
Bridgman R.
C. Callen G. Charnoff Joe Williams, Jr.
NRC Resident Inspector at Cook Plant Bridgman
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STATE OF NEW YORK )
COUNTY OF NEW YORK)
R.
S. Hunter, being duly sworn, deposes and says that he is the Vice President of Licensee Indiana 6 Michigan Electric Company, that he has read the foregoing response to Generic Letter No. 82-05 and knows the contents thereof; and that said contents are true to the best of his knowledge and belief.
R.
S. Hunter Subscribed and sworn to before me this/0'+day of~, 19&2-Notary Pu lic
'f&TEKEEEN BARRY QOTARY f UvLtC, Stete of Vow Yorq No. 4E;x60679Z Quelilied in t.4ueens County Ceetificute lited in tfew Yotk County'<.nun>ssivu extsues ntwch 3st, lyp>
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Attachment to AEP: NRC: 0678
~ ~
In preparing this attachment we use the same format as Enclosure 1 to Generic Letter No. 82-05.
Item I.A.3.1 (Simulator Exams) it Since October 1,
1981, initial Reactor Operator or Senior Reactor Operator License Candidates have received a
simulator examination at the Zion Simulator which was administered by the Nuclear Regulatory Commission.
This practice will continue in the future.
Item II.B.2 (Plant Shieldin )
The Design Shielding Review required by the NRC in NUREG-0737 Item II.B.2, has -been completed.
The March 20, 1980 Safety Evaluation Report concurred that no major shield modifications are needed.
IE Inspection Report No.
50-315/81-26 and No.
50-316/81-'29 dated December 21, 1981 stated that "It appears that the licensee has met the intent of this long-term NUREG-0737 item".
Item II.B;3 (Post Accident Sam lin )
This is to reconfirm the dates established for implementation of Item II.B.3 of NUREG-0737 in our letter No.
AEP:NRC:0652 dated December 23, 1981.
These dates are 30 days after the end of the 1982 refueling outages for both Unit's post accident sampling systems.
These refueling outages are currently scheduled for June-August (Unit 1) and October-December (Unit 2).
The installation of these systems have essentially been completed.
The components and systems are now being preoperationally tested.
It is anticipated'hat they will be fully operational in the near future;
- however, we request that the dates given in AEP:NRC:0652 remain as reconfirmed should further unanticipated equipment problems arise.
The interim post-accident system will - remain operational until the new post-accident sampling system is fully operational.
Item II.B.4 (Trainin for hfiti atin Core Dama e)
The Training Program associated with Core Damage Mitigation was completed for required plant personnel prior to October 1,
1981.
The Training Coordinator will ensure that Core Damage Mitigation Training is conducted in preparation for operator licensing and during the Shift Technical Advisor Training, and for all other plant personnel designated as requiring this training.
Item II.E.1.2 (Aux Peedwater Initiation & Plow Indication)
The revisions made to D.
C.
Cook Plant to conform to the requirements of Item II.E.1.2 were installed and operational prior
to July 1, 1981.
The NRC Safety Evaluation Report dated June 16, 1981 accepted our design and closed out this item.
Recent instrument failures caused the temporary removal of the low suction pressure trip from service on the Unit 1
motor-driven aux.
feedwater pumps.
These instruments have been repaired and returned to service.
Additional equipment is being purchased to protect these instruments.
These new devices will be installed during the upcoming refueling outages for each Unit.
Item II.E.4.2 Part 5 and Part 7 (Containment Isolation De endabilit )
The NRC Safety Evaluation Report closing out these items was issued on October 30, 1981.
Item II.F.1.(1) (Noble Gas Monitors)
This is to reconfirm the dates established in AEP:NRC:0652 dated December 23, 1981 requesting an extension to 30 days after the end of the refueling outages in 1982 for both Units 1 and 2
Noble Gas Monitors.
These refueling outages are currently scheduled for June-August, 1982 (Unit 1) and October-December, 1982 (Unit 2).
The extensions were originally requested due to equipment procurement
- problems, unexpected equipment malfunctions, difficulty in obtaining proper calibrations and preoperational testing.
The requested, extension should permit the completion of the monitor system bringing it to a fully operational stage.
The previously existing containment radioactivity level monitoring equipment will remain operational until the upcoming refueling outages.
Item II.F.1.(2)
(Sam lin
& Anal sis Of Plant Effluents)
We are requesting an extension to 90 days after the end of the refueling outages in 1982 for implementation of the final system configuration for Sampling and Analysis of Plant Effluent.
The refueling outages are currently scheduled for June-August (Unit
- 1) and October-December (Unit 2).
Equipment procurement problems have been encountered.
A portion of the necessary devices have been delivered,
- however, additional equipment is necessary to provide the final system configuration.
In addition, we have recently determined that certain design and installation modifications must 'be undertaken in order for the new system to fully meet NRC requirements.
In spite of this we believe that the requested extension should permit completion of the sample and analysis system bringing it to a fully operational stage.
During December 1979 a temporary system for collection and/or monitoring of particulate, Iodine and Noble Gas was installed on
each Unit particulate and radiogas detector.
This installation together with the equipment available in the plant counting rooms is sufficient on an interim basis to provide a sample and analysis of plant effluents.
Item II.F.1.(3) (In-Containment Area Monitor)
This is to reconfirm our request for an extension to 30 days after the end of the 1982 refueling outages for both Units 1 and 2
for installation of the InContainment Area Monitor.
The refueling outages're currently scheduled for June-August (Unit 1) and October-December (Unit 2).
The In-Containment Area Monitors together with their electrical appurtenances were installed during the 1981 refueling outages for both Units 1
and 2.
- However, certain electrical connection items were not environmentally qualified.
Me now have suitable materials but a Unit shutdown is required to perform this work and preoperationally test the system.
The configuration together with the previous existing containment area monitors will remain operational until the final "as-qualified" configuration is fully operational.
Item II.F.1.(4) (Containment Pressure Indication)
The revisions made to D.
C.
Cook Plant to conform to the requirements of Item II.F.l.(4) were installed and operational prior to January 1, 1982.
Item II.F.1.(5) '(Containment Mater Level)
The revisions made to D.
C.
Cook Plant to conform to the requirements to Item II.F.1.(5) were installed and operational prior to January 1,
1982.
Item II.F.1.(6)
(H dro en Monitorin )
This is to reconfirm the dates of 30 days after the end of the 1982 refueling outages for both Unit's hydrogen monitoring system.
These refueling outages are currently schedule for June-August (Unit-1) and October-December (Unit-2).
The installation of these systems have essentially been completed.
The
,. components and systems are now being preoperationally tested.
It is anticipated that they will be fully operational in the near future;
- however, we request that the extended dates remain as reconfirmed should further unanticipated equipment problems arise.
The existing hydrogen monitoring system will remain operational until the new hydrogen monitoring system is fully operational and the appropriate Technical Specification changes issued.
I v
The status of the applicable items of Enclosure 2 to Generic Letter No. 82-05 are presented below.
Item II.B.'1 (Reactor'Coolant S stem Vents)
" Installation of the venting system was completed during 1981.
We are awaiting the NRC's acceptance of the Reactor Coolant System vent design and the guidelines for its operation.
Item II.D.1'(Relief and Safet Valve Test Re uirements)
EPRI has completed the valve test prog'ram and we currently evaluating the test results.
As stated in our April 7, 1982 submittal to the NRC (AEP:NRC:0585B),
we may'ot be able to complete our evaluation by July 1, 1982.
Item II.E.l.l. (Aux. Feedwater S stem Evaluation)
Completed.
Item II.E.4;1 (Dedicated H dro en Penetration)
Completed.
Item II.F.2.3 (Inade 'uate Core Coolin Instrumentation)
The RVLIS equipment,'ncluding transmitters, sensing lines, electrical cabling and electronics cabinetry is physically installed in both Units.
- However, calibration difficulties have been encountered on the electronics.
It is anticipated that these difficulties can be resolved in the near future.
Items II.K.2.13, II.K.2.17. II.K.3.1 II.K.3.5 II.K.3.25 and II.K.3.30 All required information for these items has been submitted to the NRC.
Item II.K.2.19'(Se uential AFW Flow Anal sis)
Resolved.
C