ML18004B789
| ML18004B789 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 04/23/1987 |
| From: | Watson R CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| HO-870414-(O), NUDOCS 8704290099 | |
| Download: ML18004B789 (5) | |
Text
ACCESSION NBR FACIL: 50-400 AUTH. MANE WATSONI R. A.
RECIP. MANE REGUj INFORNATION DISTRIBUT STEN (RIDS)
- 8704290099 DOC. DATE: 87/04/23 NOTARIZED:
NO Shearon Harv is Nuclear Powev Planti Unit li Carolina AUTHOR AFFILIATION Carolina Powev 8< Light Co.
RECIPIENT AFFILIATlON Document Contv'ol Bvanch (Document Control Desk)
DOCKET 8 05000400
SUBJECT:
Forwards changes to procedure described in FSAR v e power ascension test program power escalation> per 10CFR50. 59.
Proceduv e purpose is to provide administrative guidelines for testing at specific power level plateaus.
DISTRIBUTION CODE:
BOOID COPIES RECEIVED: LTR / ENCL /
SIZE:
TITLE: Licensing Submittal:
PSAR/FSAR Amdts LLi Related Cov respondence NOTES: Application fov'ev'mit v'enewal filed.
05000400 REC IP IENT ID CODE/NANE PD2-1 LA BUCKLEY'S B INTERNAL:
ACRS ARM TECH ADV NRR DEST/PSB NRR/DEBT/RSB N
EPB G FIL 01 EXTERNAL:
ARJ i/DCB (ANDTS)
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NRC PDR PNL GRUEL' COPIES LTTR ENCL 1
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CSEE Carolina Power & Light Company HARRIS NUCLEAR PROJECT P. 0.
Box 165 New Hill, North Carolina 27562 APR 25 egg File Number'SHF/10-13510C Letter Number:
HO-870414 (0)
U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTN:
NRC Document Control Desk SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 REPORT IN ACCORDANCE WITH 10CFR50.59 Gentlemen:
In accordance with Title 10 to the Code of Federal Regulations, Part S0.59, the enclosed report is submitted.
This report fulfills the requirement for a written report within thirty (30) days of a change to the Initial Test Program described in Section 14 of the FSAR as required by i>cense condition 2.C.4.
This report contains a brief description of a procedure which changes the description given in the FSAR.
The description also contains a brief summary of the safety evaluation which shows that the change does not involve an unreviewed safety question or require a change to technical specifications.
Very truly yours, RAW:MW/lmj Enclosure R. A. Watson Vice President
'arris Nuclear Project cc'.
Dr. J.
N. Grace (NRC-RII)
Mr. G. Maxwell (NRC-SHNPP) 87042'VOOV9 870423 PDR ADOCK 05000400 F'DR MEM/HO-870414(0)/PAGE 1/OS1
0
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CHANGE TO PROCEDURE DESCRIBED 1N FSAR 9100-S-01, Rev. 2, Change g17y Power Ascension Test Program - Power Escalation The purpose of this procedure is to provide administrative guidelines for testing at specific power level plateaus.
The procedure provides the sequence and method of approval to increase reactor power to the next test power plateau.
Test procedure 9100-S-01 has been changed to delete the requirement for the Main Steam/Feedwater Test at the 90X power plateau.
Reg.
Guide 1.68 Appendix A, Sect.
5v requires verification that the main steam system and feedwater systems operate in accordance with design performance requirements at the 25, 50, 75 and 100X power levels.
Because the main steam/feedwater test is not required at the 90X power plateau by Reg.
Guide 1.68 and because adequate data is being obtained at the other required plateaus, this test will not be performed at the 90X plateau as presently described by FSAR Sect.
14.2.12.2.27.
~safet Omission of the subject test as described above does not
~Summer:
increase the probability or consequences of analyzed accidents, nor introduce a different type of accident or equipment malfunction than already evaluated in the FSAR.
Thus no unreviewed safety question exists.
MEM/H0-870414(0)/PAGE 3/OS1