ML20065C095
| ML20065C095 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 02/14/1983 |
| From: | Kemper J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| REF-PT21-83 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8302230725 | |
| Download: ML20065C095 (1) | |
Text
A_
G PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 1881 -1981 PHILADELPHI A. PA.19101 JOHNS.KEMPER V IC E-PR ESI D E N T FEB 141983 9
h )9 Mr. Ronald C. Haynes, Director Office of Inspection and Enforcement Region I 3
United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Subject:
Significant Deficiency Report No. 70 General Electric Local Instrument Panel Piping Limerick Generating Station, Units 1 and 2
Attachment:
Letter General Electric Company to USNRC Regions I and IV, November 18, 1982 File:
QUAL 2-10-2 (SDR #70)
Dear Mr. Haynes:
The attached letter has brought to our attention a deficiency in the General Electric supplied local instrument panel piping diagram which resulted in a potential incorrect interface with the RPV vessel instrumentation P&ID.
This deficiency has been previously reported to the USNRC under the provisions of 10CFR, Part 21.
We consider the deficiency described in the Attachment as a significant deficiency per 10CFR50.55(e) and are hereby notifying you as required.
We believe that the General Electric Company report submitted under the provisions of 10CFR, Part 21 provides the information required for 10CFR50.55(e) reporting.
Therefore, we anticipate that this letter will be our only report to you on this subject.
We will of course assure that the local instrument panel piping is corrected in accordance with the instructions received from the vendor.
Sincerely, lbY/Cf Copy to: Director of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, DC 20555 S.K. Chaudhary, USNRC Resident Inspector fhh f
O S
G E N E R A L () E LE CTR IC NUCLEAR POWER SYSTEMS DIVISION CENERAL ELECTRIC COMPANY,175 CURTNER AVE., SAN JOSE, CAUFORNIA 95125 MFN 173-82 MC 682 (408) 925-5040 CAC 89-82 November 18, 1982 U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Washington, D. C.
20555 Attention:
Richard C. DeYoung
SUBJECT:
10CFR PART 21. REPORTABLE CONDITION LOCAL INSTRUMENT PANEL PIPING This letter is to infom the NRC of a reportable defect per 10CFR Part 21, as reported to W. R. Mills of your office by C. A. Cameron, Manager of Safety Evaluation Programs on November 18, 1982.
The defect is an error on four local instrument panel piping diagrams which resulted in a potential incorrect interface with the reactor pressure vessel instrument piping. A local instrument panel contains transmitters used to monitor the reactor pressure vessel water level and pressure. The attached evaluation identifies all pertinent infomation required by 10CFR Part 21. Although the condition is reportable, the plant could not have begun operation without the defect being detected.
The defect occurred only on the Limerick 1 and 2 plants. No operating plants are affected. General Electric has infomed the Philadelphia Electric Company of the defect and the actions required for correction.
Very truly yours, G enn G. She oo, Manager Nuclear Safety and Licensing Operation cc:
L. S. Gifford, GE - Bethesda W. R. Mills, NRC R. C. Haynes, NRC - Region I U. Potapovs NRC - Region IV R. C. DeYoung, NRC (2 extra copies)
Q2MMCGM s,3,
l REPORTABLE CONDITION 1.
Name and address of the individual or individuals informing the Commission.
Dr. Glenn G. Sherwood, Manager of Safety and Licensing Operation, General Electric Company,175 Curtner Avenue, San Jose, California, 95125.
2.
Identification of the facility, the activity, or the basic component supplied for such facility for such activity within the United States which fails to comply or contains a defect.
l Interface documentation for local instrument pan 91s containing reactor water level and pressure instruments.
3.
Identification of the firm constructing the facility or supplying i
the basic component which fails to comply or cor.ains a defect.
General Electric Company, Nuclear Energy Business Operation, San Jose, California.
4.
Nature of the defect or failure to comply and the safety hazard which is created or could be created by such defect or failure to comply.
Drawing errors in the local instrument panel piping diagram resulted in a potential incorrect interface with the reactor i
pressure vessel instrumentation P&ID.
Four local panels H23-P004,
-P005, -P026 and -P027 containing water level and pressure transmitters would have been incorrectly connected at the site.
The incorrect assembly of the instruments to the reactor pressure vessel nozzle would result in the water level instruments functioning in reverse, and the pressure instruments functioning incorrectly. The instruments would register the reactor vessel water level opposite to the actual condition, i.e. high water level would register low and vice versa. Should the condition go undetected and the incorrect assembly made, the condition would severely compromise the Emergency Core Ccoling System network design basis. Safety systems that are initiated by signals from j
the water level and pressure transmitters are Reactor Protection System, Nuclear Steam Supply Shutoff System, Core Spray, High Pressure Coolant Injection, Automatic Depressurization System and Residual Heat Removal. However, this condition could never actually go undetected. The reversed instrumentation connections would be obvious beginning with the initial hydro test, pre-operation checkout, pre-operation testing and/or any attempt to startup where the instrumentation used would indicate water level t
and pressure within the reactor vessel.
5.
The date on which the information of such defect or failure to 3-comply was obtained.
November 16, 1982 j
1 e
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Page 2 6.
In the case of a basic component which contains a defect or fails to comply, the number and location of all such components in use at, supplied for, or being supplied for one or more facilities or activities subject to the regulations in this part.
This condition is unique to the Limerick Power Station and has been isolated to only four panels identified as H23-P004, -P005, -P026 and -P027.
7.
The corrective action which has been, is being, or will be taken; the name of the individual or organization responsible for the j
action; and the length of time that has been or will be taken to l
complete the action.
Field Deviation Disposition Requests have been issued by the General Electric Company to the Philadelphia Electric Company, l
defining and authorizing necessary corrective changes to the l
instrument panels. Corrective action documents and their issue l
dates are:FDDRs HHI-1467 9/17/82 and HHI-1343 - 5/22/82.
8.
Any advice related to the defect or failure to comply about the facility, activity, or basic component that has been, is being, or l
will be given to purchasers or licensees.
None.
o