ML20052G241
| ML20052G241 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 05/10/1982 |
| From: | Randazza J Maine Yankee |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.3.1, TASK-2.B.2, TASK-2.B.3, TASK-2.B.4, TASK-2.E.1.2, TASK-2.E.4.2, TASK-2.F.1, TASK-TM GL-82-05, GL-82-5, MN-82-90, NUDOCS 8205140441 | |
| Download: ML20052G241 (4) | |
Text
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EDISON DRIVE MAIM MdHARHEE Amml0 Pol'KRCOMPAR9*
i AUGISTA, MAINE 04336
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(May 10, 1982 MN-82-90 i o>
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United States Nuclear Regulatory Commission
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Washington, D.C.
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f Attention: Mr. Robert A. Clark, Chief
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Division of Licensing Office of Nuclear Reactor Regulation y
References:
(a) License No. DPR-36 (Docket No. 50-309)
(b) USNRC letter to MYAPCo. dated March 17, 1982 (c) MYAPCo. letter to USNRC dated April 16, 1982, MN 82-79
Subject:
Post-TMI Requirements (Generic Letter No. 82-05)
Dear Sir:
Enclosed are responses to Reference (b) which requested Maine Yankee to furnish the subject information pursuant to 50.54(f).
We trust the attached information is satisfactory.
If you have any further Questions, please contact us.
Sincerely, MAINE YANKEE ATOMIC POWER COMPANY
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" John B. Randazza J
Vice President Enclosure j
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- 1. Resoonses to Request (3 pages)
STATE OF MAINE
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)ss COUNTY OF KENNEBEC)
Then oersonally appeared before me, John B. Randazza, who, being duly sworn, did state that he is Vice President of Maine Yankee Atomic Power Company, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Maine Yankee Atomic Power Company, and that the statements therein are true to the best of his knowledge and belief.
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MAINE YANKEE ATOMIC POWER COMPANY Enclosure to MYAPCo letter to USNRC dated May 10, 1982, MN-82-90 I. A. 3.1 Simulator Exam This items was completed October J ISee MYAPCo letter FMY-81-153, October 6,1981)
- II.B.2 Plant Shieldirq Our review of the Shielding Desigt
.ew letter dated November 6,1980, WMY-80-147, indicates only one it tnat has not yet been completed; reach rods have not been installed on twv valves required for Residual Heat Removal system operation.
This modification will be addressed by the.end of 1982.
We believe this schedule is acceptable because of the many alternative decay heat removal paths and redundant equipment available at Maine Yankee including three steam generators and three full size auxiliary feedwater pumps.
II.B.3 Post Accident Sampling Capability 1.
Coolant Sampling: System installation was completed April 1,1982 however two pressure sensors have been returned to the manufacturer for repair.
The system will be calibrated and tested upon return of-the sensors and it is anticipated that it will be operable by July 1, 1982.
2.
Containment Atmosphere Sampling - This item was complete as of April 1, 1982.
3.
Chloride Sampling - In accordance with NUREG-0737, Item II.B.3 clarification paragraph (5), Maine Yankee can complete the analysis in 4 days as required.
No system modifications were necessary.
II.B.4 Trainino for Mitigating Core Damage This item was complete as of November 15, 1981.
(See: MYAPCo. letter to USNRC dated September 28,1981, FMY81-144)
II.E.1.2 Auxiliary Feedwater Initiation and Flow Indication 1.
Initiation - Safety Grade:
The total system logic was installed and operable as of January 1,1981.
During the 1982 refueling outage, isolation valves will be upgraded to safety grade and redundant isolation valves will be added to provide single failure protection.
2.
Indication - Safety Grade: Flow indication system was installed and made operable as of May 1,1981.
l
MAlWE VAMKEE ATOMIC POWER COMPANY II.E.4.2 Containment Isolation Dependability 5.
Pressure Setpoint - No modifications were necessary.
(See USNRC letter to MYAPCo. dated January 18, 1982) 7.
Radiation Signal To Close Purge Valves - No modifications were necessary. The containment purge and vent isolation valve do close on a high radiation signal.
II.F.1 Accident Monitoring 1.
Noble Gas Monitor - Installation es complete as of March 1,1982.
Pending testing and installation of shielding,. it will be operable by June 1, 1982 Main Steam Line Monitors - Installation was complete as of March 1, 1982.
However, operational problems have been experienced which are being pursued with the manufacturer.
2.
Iodine / Particulate Sampling - This capability was in effect as of April 1, 1982.
3.
Containment High-Range Monitor - This item was complete as of April 1, 1982 and is operable.
4.
Containment Pressure Monitor - This item was complete as of April 1, 1982 and is operable.
5.
Containment Water Level - This item was complete as of January 1, 1982, and is operable, however, the' level transmitter is not qualified to IEEE323.-74 criteria.
The existing sump level transmitter is qualified to 1971 criteria and is the best available until testing is completed on the unit to current requirements.
This transmitter only provides sump level indication and has no safety function.
Therefore, failure of this unit will not affect the safe shutdown of the plant because indications required for operation of the recirculation system are available outside containment, such as discharge pressure of the HPSI and spray pumps and HPSI flow.
Qualification of this transmitter will be oursued in connection with the environmental qualification issue.
(See MYAPCo. letter to USNRC dated February 25, 1982, MN-82-04) 6.
Hydrogen Monitor a.
One qualified monitor was installed during March 1982 and will be operable pending the development of operating procedures and installation of thermal insulation on the inlet sample line. We anticipate that it will be operable by the 1982 refueling outage, b.
The other monitor is operable but it is not environmentally qualified and will have to be moved in order to meet II.B.2 shielding requirements.
This will be done during the 1982 refueling outage.
j
MAINE YANKkE ATOMIC POWER COMPANY Until the qualified hydrogen monitor is" operable, Maine _ Yanke'e
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- will take appropriate actions to initiate containment h' drogen
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purge on the seventeenth day-'followingj e LOCA if the existing unaualified hydrogen analyzer is not accessible to monitor
- hydrogen generation. -(See MYAPCo. letter to USNRC dated February 25, 1982,. W4-82-34) i-l i
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