IR 05000400/1986002
| ML18019A610 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 02/11/1986 |
| From: | Jape F, Mathis J, Taylor P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18019A609 | List: |
| References | |
| 50-400-86-02, 50-400-86-2, NUDOCS 8603050529 | |
| Download: ML18019A610 (8) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 Report No.:
50-400/86-02 Licensee:
Carolina Power and Light Company P. 0.
Box 1551 Raleigh, NC 27602 Docket No.:
50-400 Facility Name:
Harris
License No.:
CPPR-158 Inspection Conducted:
January 7-11, 1986 Inspectors:
. C2 I P.
A. Tayl o J.
this Approved by F. Jape, ction Chief Engineering Branch Division of Reactor Safety e 7 Date Signed z-p g4 Date Signed
~/ufj6 Date Signed SUMMARY I
Scope:
This routine, unannounced inspection entailed 70 inspector-hours on site in the areas of hot functional test witnessing and preoperational test procedure review.
Results:
No violations or deviations were identified.
po03050>~9 860218 ABACK 05000q00 PDR
REPORT DETAILS 1.
Persons Contacted Licensee Employees
"J.
L. Willis, Plant General Manager
- C. S. Hinnant, Manager Startup
"C.
L. McKenzie, Director Quality Assurance/Quality Control (QA/QC)
Operations
'G. T.
Lew, Startup Supervisor, Technical/Administrative Support
~C.
Rose, QA Supervisor, Operations
"D. L. Tibbitts, Project Specialist, Regulatory Compliance B. Clark, Startup Engineer G. Michie, Startup Engineer A. Pietrovich, Startup Engineer E.
Cook, Startup Engineer Other licensee employees contacted included technicians, operators, and office personnel.
NRC Resident Inspectors
'G.
F. Maxwell
"S.
P. Burris
"Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on January 11 1986, with those persons indicated in paragraph above.
The inspector described the areas inspected and discussed in detail the inspection findings.
No dissent-ing comments were received from the licensee.
The following new items were identified.
a.
Inspector Followup Item 400/86-02-01, Identify System Conditions to Meet Regulatory Guide 1.68, Revision 2 Appendix A, Section 1.i for Testing Containment Isolation Valves paragraph
b.
Unresolved Item 400/86-02-02, Test Procedure 1-2060-P-01 and 1-8010-P-02 Data Sheets Do Not Identify Data Recorder~aragraph
C.
d.
Inspector Followup Item 400/86-02-03, Confirm Method for Timing Pres-surizer PORV Block Valves, Test Procedure 1-2005-P-04 paragraph
Inspector Followup Item 400/86-02-04, Confirm Method for Timing Main Steam Isolation Valves (MSIV)
and Bypass Valves, Test Procedure 1-3020-P-02 - paragraph
P
e.
Unresolved Item 400/86-02-05, Set Point Verification of Main Steam Safety Valves, Test Procedure 1-3020-P-06 - paragraph 6.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspection.
3.
Licensee Action on Previous Enforcement Matters This subject was not addr essed in the inspection.
4.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or devia-tions.
New unresolved items identified during this inspection are discussed in paragraph 6.
5.
Preoperational and Integrated Hot Functional Test Witnessing (70308, 70312, 70314)
a
1-2005-P-Ol, Revision 1, Hot Functional Test (HFT)
During this inspection the licensee had initiated heatup of the reactor coolant system (RCS)
for the purpose of testing and observing the integrated operation of plant systems at no load operating temperature and pressure.
The inspectors observed control room activities during the heatup to verify that the controlling procedure for HFT contained the latest revision, procedure changes, and also to observe the conduct of control room operators and startup engineers.
The inspectors reviewed HFT controlling procedure prerequisites and initial conditions to verify that these items were met during RCS heatup.
Personnel staffing from the startup group to support HFT was divided into three shifts consisting of a shift test engineer, HFT coordinator, startup engineers and technicians.
Support from the operational group consisted of senior reactor operators, reactor operators and auxiliary unit operators with coverage being provided on two twelve hour shifts.
The inspectors noted that operating personnel were using plant operating procedures for aligning and operating systems and also for the purpose of checking out their adequacy.
The heatup to no load conditions was delayed at the 400'F 500 F
plateau due to high pH chemistry in the steam generators and the of.25 (pH specification is 8.5 - 9.2).
In addition the condensate storage tank (CST) dissolved oxygen concentration was out of specifi-cation at approximately 400 parts per billion (PPB)
( specification
<100 PPB).
The major contributor to the high pH appeared to be the normal breakdown of hydrazine at elevated temperature.
When the chemistry problems were corrected in the steam generators and CST RCS heatup continued to achieve no load condition Within the areas inspected, no violations or deviations were identified.
b.
Preoperational Test Witnessing The inspectors witness portions of those tests listed below to verify that these tests were being performed in accordance with an approved procedure, test data are being recorded properly, revisions and proce-dure changes were current and that equipment on component problems when applicable were being handled in accordance with administrative controls.
(1)
1-2090-P-02, Revision 0, Emergency Core Cooling System Check Valve Leakage Test The purpose of thi s test is to demonstrate the integrity of the accumulator discharge check valves and the low head safety injection system check valves by verifying that the individual check valve seat leakage rate meets the acceptance criteria of
gallon per minute or less.
This procedure also measures the response time of containment isolation valves SI-263 and SI-264.
The inspector witnessed the testing of accumulator check valves SI-249 and SI-250, section 6. 1.
Upon completion of the test the results were inconclusive.
The test was determined to be affected by the interface temperatures at the check valves (approximately 450 F on one side of the check valve and ambient temperature on the other side).
It was concluded that additional time between filling and depressurization of the piping was necessary to reach equilibrium conditions.
The test was repeated and satisfactory results were obtained.
The inspectors reviewed the results of the response time test for containment isolation valves SI-263 and SI-264.
The response time appeared to meet the acceptance criteria of
seconds or less.
The inspectors noted that the initial condition section of the test procedure did not identify the system conditions under which the containment isolation valves were to be tested.
This area is identified as Inspector Followup Item 400/86/02-01, Identify System Conditions to Neet R.G.
1.68 Revision 2, Appendix A, Section l.i. for Testing Containment Isolation Valves.
(2)
1-8010-P-02, Revision 0,
Containment Building Hot Penetration Testing The inspectors witnessed portions of the preoperational test, 1-8010-P-02, Containment Building Hot Penetration.
In general, the test demonstrated that the reactor containment concrete temperature in the vicinity of the hottest penetrations did not exceed 200'F during Hot Functional Testing (HFT).
~
~
V The test was performed at five different temperature plateaus starting with 150'F thru 557'F.
The inspectors witnessed Section 6.4 to observe overall test personnel performance, verify that an approved procedure was available and in use, test equip-ment was properly calibrated, and deficiencies identified during testing was properly documented.
For the various temperature plateaus the inspectors verified that the licensee recorded concrete temperatures every five minutes for each penetration until three successive recordings were within each other by 3 F.
No violations or deviations were identified in the areas inspected.
6.
Preoperational Test Procedure Review (70300, 70347, 70335)
The inspectors reviewed the following preoperational test procedures:
1-2060-P-01, 1-2005-P-04, 1-3020-P-06, 1-3020-P-02, Revision 0, Chemical Volume Control System (CVCS) Hot Functional Test Revision 2, Pressurizer Pressure and Level Test Revision 0, Set Point Verification Main Steam Safety Valves Revision 0,
MSIV/PORV Hot Functional Testing These procedures were reviewed to verify that the technical content in the procedures was consistent with FSAR Chapter 14.2 and R.G.
1.68, Revision
requirements and commitments.
The test procedures were also reviewed to verify that the requirements of Harris Plant Startup Manual Volume
have been incorporated into the test procedures regarding preparation, reviews, management approval, procedure format and the required prerequisites, precautions, initial conditions and acceptance criteria.
The review resulted in comments to four test procedures as follows:
a.
1-2060-P-Ol, Revision 0, CVCS Hot Functional Test The inspectors noted that test procedure data sheets provided in section 10. 1 through 10.8 did not have a verification signature to identify the data recorder, in addition test procedure 1-8010, Revision 0,
Containment Building Hot Penetration did not identify the data recorder for data sheets provided.,in section 10. 1 through 10.7.
The issue of not identifying the data recorder on data sheets was brought to the licensee attention at an NRC exit interview on December 20, 1985, and was described at that time~ potential Violation of 10CFR50, Appendix B Criterion XVII in Inspection Report No. 400/85-47.
These items are considered to be further examples of a previously identified problem and is identified as, Unresolved Item 400/86-02-02, Test Procedures 1-2060-P-01 and 1-8010-P-02 Data Sheets Do Not Identify Data Recorder.
It should be noted that the licensee has initiated a review of preoperational test procedures and has issued a memorandum to the startup group addressing this subjec b.
1-200S-P-04, Revision 2, Pressurizer Pressure and Level Test The test procedure acceptance criteria requires that the pressurizer power operated relief valve (PORV) block valves meet a closure time of less than 10 seconds.
The inspectors noted that the timing method used in section 6.0 of the test procedure requires that the block valve open and close status lights were used and a hand-held stop watch was used to obtain the closure times.
The inspectors questioned the accuracy of this method versus starting the timing from the turn of the block valve control switch at the main control board and stopping the time when the closed status light was received.
This is identified as an Inspector Followup Item 400/86-02-03, Confirm Method for Timing Pressurizer,PORV Block Valves.
c.
1-3020-P-02, Revision 0, MSIV/PORV Hot Functional Test The method for timing the closure of the MSIV and main steam bypass valves was by utilizing a strip chart recorder.
The inspectors questioned whether the strip chart recorder picks up the time when the MSIV bypass valve control switch is turned at the main control board.
The licensee indicated that the test switches and recorder arrangement would obtain the time at the turn of the MSIV - bypass valve control switch.
This will be further reviewed during a
subsequent inspection and is identified as Inspector Followup Item 400/86-02-04, Confirm Method for Timing the MSIV and Bypass Valves.
d.
1-3020-P-06, Revision 0,
Setpoint Verification of Main Steam Safety Valves Draft Technical Specification Table 3.7-2 contains footnote 'which states.
The lift setting pressure shall correspond to ambient condi-tion of the valve at nominal operating temperature and pressure.
The licensee indicated that the Technical Specification footnote would be reviewed and its application for testing the main steam safety valves incorporated into the test procedure.
This area is identified as Unresolved Item 400/86-02-05 Set Point Verification of Main Steam Safety Valves, Test Procedure 1-3020-P-06.
Within the areas inspected, no violations or deviations were identifie f A