ML20086Q258
| ML20086Q258 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/01/1973 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8402270490 | |
| Download: ML20086Q258 (2) | |
Text
-
~
o o
PHILADELPHIA ELECTRIC COMPANY 0[h.
2301 MARKET STREET
/
, g T./
1 kij',\\.
- /
PHILADELPHIA. PA.19101 V
.s azisi e4i 4ooo
\\-
,.x,>'
' fj w.-cr\\/
' h.' i.1W October 1, 1973 Mr. A. Giambusso Deputy Director of Reactor Projects United States Atomic Energy Commission Directorate of Licens8ng Washington, D.C.
20545 Reference Peach Bottom Atomic Power Station - Unit 2 Facility Operating License DPR-44 Docket No. 50-277 Subiect:
Abnormal Occurrence
Dear 1r. Giambusso:
On September 22, 1973 temperature switch TS-2-12-99 was found to be out of calibration., This setpoint shif t was reported to Mr. Tom Shedlowsky, A.E.C. Region 1, Regulatory Operations Office on September 24, 1973.
In accordance with Section 6.7.2.A of the Technical Specifi-cation Appendix A of DPR-44 for Unit 2 Peach Bottom Atomic Power Station, these sotpoint shi f ts are being reported to the Directorate of Licensing as Abnormal Occurrences.
TE-2-12-98/TS-2-12-99 During routine instrument surveillance testing on 9/22/73, temperature swi tch TS-2-12-99 was found to be out of calibration.
This switch supplies the Reactor Water Cicanup System High Temperature trip signal to isolate the system on High Non-Regenerative Heat Exchanger Discharge Temperature. The Technical Specification limit is
$_140 F (Tabic 3.2.A).
The "as found" trip setting was 141.2 F.
Investi ga tion:
During the Pre-operational Testing program, this switch had been set at approximately 1400F. This setpois.t did not allow sufficient margin below the specification limit.
y ',l((
gM[oS s
' 7472 COPY SENT REGION -.
w
~
L
e 1.
O O
Mr. A. Giambusso October 1, 1973 Page 2 Corrective Action:
The setpoint was. changed to 130 F.
The acceptabic setpoint ranges for these and other Technical Specification limited instruments are being re-evaluated to arrive at more viable setpoints where possibic to allow a greater margin between the setpoint and the Technical Speci fication Limi t.
Safety Implications:
There are no safety implications because the instrumentation that initiates primary containment isolation is not required then primary containment integrity is not required (Technical Specification Limi ting Conditions for Operation 3.2.A).
The requirement for primary containment integrity (Technical Specification Limiting Condi tions for Operation 3.7.A.2) does not exist at this time.
Very truly yours, Mje M
J. Cooney
/
Asst. Gent. Supt.
Generation Division MJC:1pm Copy to:
M. J. P. O'Reilly Director, Region 1 United States Atomic Energy Comission i