ML18019B149
| ML18019B149 | |
| Person / Time | |
|---|---|
| Site: | Harris |
| Issue date: | 08/29/1986 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NLS-86-332, NUDOCS 8609080045 | |
| Download: ML18019B149 (4) | |
Text
REGULATO INFORNATION DISTRIBUTION 'TEN (RIDB)
ACCESSION NBR: 8b09080045 DOC. DATE: 86/08/29 NOTARIZED:
NO DOCKET ¹ FACIL:50-400 Shearon HaYris Nuclear Power Planti Unit ii Carolina 05000400 AUTH. NANE AUTHOR AFFILIATION ZINNERNANiS. R.
Carolina Power Zc Light Co.
RECIP. NANE RECIPIENT AFFILIATION DENTON> H. R.
Office of Nuclear Reactor Regulationi Director (post 85ii25
SUBJECT:
Submits addi info re instrumentation to detect inadequate core coolingi per SER License Condition
- 8. Instrumentation includes subcooling margin calculated bg emergency response facilities info sos computer 5 core exit thermocouple sos.
DISTRIBUTION CODE:
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TITLE:
OR Submittal: Inadequate Core Cooling (Item II. F. 2)
QL 82-28 NOTES:Application for permit renewal filed.
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ggQ[l Carolina Power & LIght Company AUG 2 9 1986 SERIAL: NLS-86-332 IMr. Harold-R. Denton,.Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO.
1 DOCKET NO.50-000 INADEQUATECORE COOLING INSTRUMENTATION
Dear Mr. Denton:
Carolina Power R Light Company (CPRL) hereby submits additional information concerning the Shearon Harris Nuclear Power Plant (SHNPP) instrumentation to detect inadequate core cooling. This information is submitted in response to Safety Evaluation Report (SER) License Condition No. 8. The instrumentation to detect inadequate core cooling includes the following three subsystems:
(1) subcooling margin calculated by the Emergency Response Facilities Information System (ERFIS) Computer, (2) core exit thermocouple system, and (3) Reactor Vessel Level Instrumentation System (RVLIS).
This instrumentation willbe installed and preoperational testing completed prior to fuel load. Portions of RVLIS which require data from actual reactor coolant flow measurements with the core in place willbe tested after fuel load.
The above commitments supplement CPRL's previous commitments on this instrumentation submitted by letter dated May 29, 1986.
If you have any questions or require additional information on this subject, please contact me at (919) 836-6202.
Yours very truly, 3HE/crs (0072GAS) cc:
Mr. B. C. Buckley (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Dr. J. Nelson Grace (NRC-RII)
S.
Z erman Manager Nuclear Licensing Section 8609080045 860829
'PDR kDOCK 05000400 E
, PDR 411 Fayetteville Street
+ P. O. 8ox 1551
~ Raleigh. N. C. 27602 os I g
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