ML18022A403
| ML18022A403 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 09/11/1986 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18022A404 | List: |
| References | |
| NLS-86-280, NUDOCS 8609160359 | |
| Download: ML18022A403 (5) | |
Text
REGULA Y INFORNATION DISTR IBUT1 SYSTEt'1
( R IDS)
ACCESSION NBR: 860926035'Ij'OC. DATE: 86/09/2 2 NOTARIZED: YES DOCKET I FACIL: 50-400 Shearon Hav v is Nucleav Power Plant>
Unit 1> Carolina 05000400 AUTH. MANE, AUTHOR AFFILIATION CUTTER> A. B.
Cav olina Power 8c Light Co.
RECIP. NANE RECIPIENT AFFILIATION DENTON> H. R.,
OFfice of Nucleav Reactor Regulation>
Div ectov (post 851125
SUBJECT:
Forwards Amend 34 to FSAR For Shea&on Harris Nucleav'oeer Plant Unit 2. Amend provides changes to Section
- 14. 2 v e pv e-opev'ationL testing. Justification For each change li sted.
DIBTRIDVTION CODE:
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TITLE: Licensing Submittal:
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CNK Carolina Power 8r Light Company SEP IL SERIAL: NLS-86-280 Mr. 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 FSAR AMENDMENTNO. 30
Dear Mr. Denton:
Carolina Power R Light Company (CPRL) hereby submits Amendment No. 30 to the Shearon Harris Nuclear Power Plant (SHNPP) Final Safety Analysis Report (FSAR). This amendment provides changes to Section 10.2 concerning Pre-Operational Testing.
The following provides justification for each change:
10.2.2 10.2.3.2 10.2.5.2 10.2.12.1. 16 Revisions are made to reflect a management change.
The Start-up Power Test Program responsibility is changed from the Manager Start-up to the Manager Technical Support.
Revisions are made to reflect the current Diesel Generator Test Summary Acceptance Criteria. Technical Specifications and Pre-Operational Test Procedures require a generator load sequence of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 110 percent and 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> at 100 percent.
10.2. 12.1.37 Revisions are made to reflect that the setpoint for a CCW low-flowalarm is established in CPdcL Setpoint Document CAR 2166-B-508.
10.2. 12.1.60 10.2. 12.1.62 Revisions are made concerning Process Computer Test Summary to reflect current acceptance criteria.
Revisions to RWST Test Summary are made for the following reasons:
Using water to simulate tank level is unnecessary as it is a repetition of transmitter calibra-tion procedure.
The automatic fillvalve on the RWST is replaced by a manual fill valve.
RWST level setpoints are verified in loop calibration and are established in CPRL Setpoint Document CAR 2166-B-508.
86091b03'O'V 860'Pi 1 PDR
- DOCK 05000400 PDR ~i 411 Fayettevilte Street
~ P. O. Box 1551
~ Raleigh, N. C. 27602
54r. Harold R. Denton NLS-86-270 / Page 2 10.2.12.2.6 10.2.12.2.11 The Reactor Coolant System Flow Coastdown Test Summary is revised to reflect acceptance criteria esta-blished via the Westinghouse NSSS Start-up Manual.
The Start-up Manual is used since it establishes design flow coast-down criteria at hot standby conditions which are test specific.
These hot standby conditions are consistent with the LOFTRAN code analyzed at 100-percent power which is assumed in the FSAR Chapter 15 analysis.
The Power Coefficient Measurement Test Summary is revised to reflect that the doppler power coefficient predicted C is determined from data in the Cycle No.
1 Westinghouse Nuclear Design Report.
C is not the limiting value that is established via the safety analysis, but rather an analytical prediction that is specific to a corg configuration.
The comparison of C to C validates the analytical prediction of the Nuclear Design Report.
The acceptance criteria of +0.5 is a Westinghousygeneric valy that establishes a
band around C which, if C falls within that band, demonstrates acceptable agreement between predicted and measured results.
10.2. 12.2.25 Revisions are made to reflect consistency with the Operations Surveillance Test for RCS Leakage Evaluation.
10.2.12.2.26 10.2.12.2.31 The Natural Circulation Flow Test Summary is revised to reflect the deletion of flow data due to inaccuracies in flow measurement and the use of thermocouple data for a more realistic power distribution.
Revisions are made to reflect the proper Steam Generator Test for Condensation Induced Water Hammer.
Each revised page bears the amendment number, and technical changes are indicated by vertical bars in the page margin. Instructions for inserting revised pages are included.
Mr. Harold R. Denton NLS-86-270 / Page 3 If you have any questions regarding this amendment, please contact me.
Your very tr l, ABC/GB/vaw (00283DK)
Enclosure A. B. Cutter - Vice esident Nuclear Engineering
&. Licensing cc:
Mr. B. C. Buckley (NRC)
Mr. G. F. Maxwell (NRC-SHNPP),
Dr. 3. Nelson Grace (NRC-RII)
Wake County Public Library A. B. Cutter, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, contractors, and agents of Carolina Power R Light Company.
My commission expires:
5-IB R otary S