05000289/LER-1976-045, Forwards LER 76-045/03L.Provides Supplemental Info
| ML19261F173 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/30/1976 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19261F174 | List:
|
| References | |
| GQL-1763, NUDOCS 7910250588 | |
| Download: ML19261F173 (3) | |
| Event date: | |
|---|---|
| Report date: | |
| 2891976045R00 - NRC Website | |
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U.S. NUCLE AR REGULATORY <
'Sio N OoCKET NUMBE R 50-239 (2 78)
"'NCIN![TREPORT NRC DISTRIBUTION FoR PART 50 DOCKET M ATERI AL I
TO.
FROM:
DATE oF DOCUMENT Metropolitan Edison Company 12/30/76 Mr. J. P. O'Reilly Reading, Pa.
DATE RecEivEo R. C. Arnold 1/13/77
% ETTER ONoToRIZED PROP t.JPUT F oRM NUMBER oF COPIES RECEIVED NoRIGIN A L D NC LASSIFIE D OccPY One SiRUed
DESCRIPTION
ENCLOSURE Ltr. trans the followings Licensee Event Report (R0 50-289/76-45/3L) on 12/8/76 concerning radiation monitor RM-A2 being removed from service for repairs which constituted operation in a degraded mode permitted by a limiting condition for operatica.
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Three Mile Island #1 NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KRECER/J. COLLINS FOR ACTION /INFOR.*1 ATION 1/14/77 RJL X' BRANCH CHIEF:
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HANAUER X TEDESCO/MACCARY X
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- h noe ran ~xans METROPOLI FAN EDISON COMPANY POST OFFICE BOX 542 READING, PENNSYLVANI A 19603 TELEPHONE 215 - 9294 601 Dece=ber 30, 1976 GQL 1763 Mr. J. P. O'Reilly, Director Office of Inspections and F.rforcement, Regien I t[d y r,~ 'I f
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Dear Cir:
N Docket No. 50-289 Cperating license No. DPR-50 In accorlance with the Technical Specifications of cur Three Mile Island
- iuclear Station Unit 1 (DfI-1), we are reporting the following reportable occurrence:
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(1) Report :lu=ber: 76 h5/3L y',
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V (2a) Required Report Date: 01/07/77 wM, 07' v s ec,
(2b) Date of Occurrence: 12/08/76 v5lllj f s (3) Facility: Three Mile Island :Iuelear Station - Unit 1 (L) Identification of Occurrence:
Title: Radiation Monitor Pa!-A2 Removed frc= Service for Repairs.
Type:
A reportable occurrence as defined by Technica] Specification 6.9 2.3. (2) in that a radiation =onitor RM-A2 vac re=cved frc=
service for corrective maintenance which ccnstitutes operation in a degraded =cde per itted by a limiting condition for operation as defined by Technical Specification paragraph 3.6.6.7.
(5) Conditions Prior to Occurrence:
Power:
Core 2531 =vt RC Temp.
579cy 7 37e, Elec.
850 =ve PRZR Level 215 inches RC:
Flow 1k0 x 106 lbs/h*
emp.
6500 F cn": c RC:
Pressure 2155 psi 392 (481087
Mr. J.*P.
O'Reilly, Director G;L 1763 (6) Description of Occurrence:
Cn December 8,1976, at 2055 hours0.0238 days <br />0.571 hours <br />0.0034 weeks <br />7.819275e-4 months <br />, radiation =cnitor RM-A2 was taken out of service to re=ove =cisture frc= the =cnitor.
I:=ediately, the =cniter was dried out and heat tracing and heat lamps were applied to the inlet piping and the =cnitor to compensate for te=perature differences which caused the buildup =cisture.
(7) Designation of Apparent Cause of Occurrence:
The cause of this cccurrence has been detem:ined to be desien in that condensation occurs because of the temperature differences between the Reactor Building, where the air sa=ple is taken, and the Intermediate Building, where EM-A0 is located.
(8) Analysis of Occurrence:
It has been determined that this occurrence did not constitute a threat to the health and safety of the public in that:
1)
A sample of the Reactor Building atmosphere was taken every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and analyzed for radioactivity as required by Technical Specificaticn paragraph 3.1.6.7. There was no abner =al radioactivity found.
2)
The =cnitor was returned to service within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> as required by Technical Specification paragraph 3.1.6.7 3)
At least 2 other means of leak detecticn vere available as required by Technical Specification paragraph 3.1.6.7 (9) Corrective Action:
In addition to the i==ediate corrective action described above, implementa-tion of Change Modification 569, which involves interchanging the existing inlet and outlet piping to sample the cooler air discharged by the Reacter Building Ventilaticn, is scheduled for the 1977 Refueling Outage.
The Plant Operations Review Cc==ittee and Unit Superintendent have reviewed and approved the above ccrrective action and have taken steps to assure its cc=pletion.
(10) Failure Data:
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Similar Events
None Sincerely,
. L F1 R. C. Arnold Vice President RCA:DGM:kl