IR 05000400/1985002
| ML18003B062 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 01/28/1985 |
| From: | Jape F, Schnebli G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18003B060 | List: |
| References | |
| 50-400-85-02, 50-400-85-2, NUDOCS 8503060173 | |
| Download: ML18003B062 (8) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 Report No.:
50-400/85-02 Licensee:
Carolina Power and Light Company 411 Fayetteville Street Raleigh, NC 27602 Docket No.:
50-400 Facility Name:
Harris
Inspection Conducted:
January 8-11, 1985 Inspector:
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License No.:
CPPR-158 Approved by:
F. Jape, Section Chic Engineering Branch Division of Reactor Safety Date Signed SUMMARY Scope:
This routine, unannounced inspection involved 22 inspector-hours on site in the areas of overall preoperational test program review and reactor coolant system hydrostatic test procedure review.
Results:
No violations o', deviations were identified.
8503060173 850130 PDR ADQCK 05000400
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4, REPORT DETAILS 1.
Licensee Employees Contacted
- C. S. Bohanan, Director, Regulatory Compliance
- N. J. Chiangi, Manager, QA/QC
- C. S. Hinnant, Manager, Startup
- G. T. Lew, Supervisor, Startup M. Pugh, Engineer, QA
- J. L. Willis, Plant General Manager NRC Resident Inspectors
- G. F. Maxwell
- R. L. Prevatte
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on January 11, 1985, with those persons indicated in paragraph 1 above.
The licensee acknowledged the findings without significant comment.
The licensee did not identify as proprietary any of the materials provided to or reviewed by'he inspector during this inspection.
Inspector Followup Item, 400/85-02-01, Simplify method of expressing tolerances or ranges in acceptance criterion - paragraph 5.
3.
Licensee Action on Previous Enforcement Matters Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
I 5.
Overall Preoperational Test Program Review (70301)
The inspector.continued the review of the Harris facility's Startup Manual (SUN),
Volume 1, Revision 19.
This document identifies the administrative controls that will be used to conduct the preoperational
'and startup test programs.
The inspector reviewed the following sections of the manual:
Section 8, Component Testing and Initial Operation Section 10, Pressure Test Program
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The above portions of the manual were reviewed-to ensure that the preoper ational test program administrative controls have been developed in accordance with commitments and requirements specified in FSAR Chapter 14.2, Preoperational Test Program; Regulatory Guide 1.68, Revision 2, August 1978, Initial Test Program for Water Cooled Nuclear Power Plants; ANSI 18.7-1976, Administrative Controls and gA for Operational Phase of Nuclear Power Plants; and ASME Code requirements.
Within the areas inspected, no violations or deviations were identified.
The inspector identified one area of concern which appears to need additional clarification:
The method for expressing the range of values in acceptance criteria should be in a form to avoid errors of addition, subtraction, or conversion.
The SUM, VOLUME I, Section 11, Step 7.2 lists the following example for acceptance criterion:
"The Fuel Pools'ooling Pumps will be +55 of 153.4 feet of head at shutoff and
+3%,
-0% of 98.2 feet of heat at 4560 gpm."
The expression of acceptance criterion in this format is susceptible to error due to the computations that must be accomplished by the test engineer during performance of the test.
A more appropriate means of expressing this acceptance criterion would be:
"The Fuel Pools'ooling Pumps will be 145.7 to 161.1 feet of head at shutoff and 98.2 to 101.1 feet of heat at 4560 gpm."
The above item was discussed with appropriate plant management and is identified as Inspector Followup Item ( IFI) 400/85-02-01, simplify method of expressing tolerances or ranges in acceptance criterion.
6.
Reactor Coolant System Hydrostatic Test Procedure Review (70362 and 70300)
The inspector reviewed the final as-issued copy of the Reactor Coolant System Cold Hydrostatic Test Procedure (SUM, Volume IV, No. 1-2005-C-01) to verify that the test procedure met the requirements and commitments specified in ASME Code,Section III, Division 1, Subsection NB, Section 6000; Regulatory Guide 1.68; Safety Evaluation Report; and the FSAR Chapter 14.2.
The inspector verified that test procedures contained the required test temperatures, test pressures in relation to ASME Code requirements, test gage calibration requirements, inspection points and preparation for inspection, N-stamp documentation, and gC verification of the test results.
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Previously Identified Inspector Fol1owup Items (Closed)
IFI 400/84-28-01, Fully identify all Joint Test Group members in the Startup Manual and provide guidance regarding restart of a test following a test interruption.
The inspector reviewed Revision 18 to the SUM which incorporated the changes required by this item.
IFI 400/84-28-01 is close Jll I'I") t w
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