IR 05000528/1982033
| ML20028F490 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/27/1982 |
| From: | Fiorelli G, Johnston G, Thomas Young NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20028F486 | List: |
| References | |
| 50-528-82-33, NUDOCS 8302010390 | |
| Download: ML20028F490 (5) | |
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U. S. NUCLEAR REGULATORY COPEISSION
REGION V
Report No. 50-528/82-33 Docket No. 50-528 License No.
CPPR-141 Safeguards Group Licensee:
Arizona Public Service Company P. O. Bot: 21666 Phocnix, Arizona 85036 Facility Name:
Palo Verde Nuclear Generating Station - Unit 1 Inspection at:
Palo Verde Site, Wintersburg, Arizona Inspection conducted: November 22,19F? - December 17, 1952 Inspectors: C bM
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elli, Serf)i r Resic t i pe Date Signed G. F
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G.Jopston,Residn Inspec Date Sioned
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T. Young, Jr., Chief f
Date Signed Reactor Projects Sectf 6 2
Sumary:
Inspection on November 22, 1982 - December 17, 1932 (Report No. 50-528/82-33)_
Areas Inspected: Facility design changes, preoperational test procedure review.
piping verification program, preoperational test witner. sing, preoperational tes; procedure verification, facility tours, an( independent effort. Tha inspection involved 149 hours0.00172 days <br />0.0414 hours <br />2.463624e-4 weeks <br />5.66945e-5 months <br /> onsite by two NRC resident inspectors.
Results: No items of ncncompliance or deviations wera identified.
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DETAILS 1.
Persons Contacted a.
Arizona Public Service Company (APS)
- G. C. Andognini, Electric Operations Vice President
- J. Bynum, Mar,:;ger of Nuclear Operations
- J. Alien, Technical *upport Manager J. Kirby, Startup Manager
- G. Pankonin, Startup 0::ality Assurance.(QA) Manager W. Craig, Startup QA Supervisor D. N. Willsey, Technical Support Superv hor C. Russo, Operations QA Manager J. Behm, Operations QA Suptrvisor D. Sanchez, Test Group Supervisor,
W. Roman, Test Engineer R. Cavalieri, Shif t Test Coordinator
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S. Penick, QA Engineer F. Jackson, Operations Support Englnter b.
Bechtel Corport'fon o
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T. Quiggle, Project Startup Supervisor C. Berg, Construction Field Superintendent The inspectors also inter-iewed other engineers and craft personnel.
- Indicates those present at exit ~ meeting.
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Facility Design Changes a.
Procedure A follow-up review was made of design change activities. The inspectors noted that a new procedure has been issued which assists in clarifying the responsibilities and logistics of Bechtel initiated design changes.
The procedure incorporates travelers which are to be used for schedule review purposes and which alert startup engineers of impending design changes. Additional clarifications identifying startup test engineer resronsibilities for documentation. This was brought to the attention of aPS.
Evaluations are still in progress to establish a final program and design change format for APS initiated and controlled design changes.
This matter will require resolution prior to receipt of an operating license.
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Installation The following three facility modifications were inspected during the period.
(1) Excess flow check valves installed in the CVCS system.
(2) Temperature elements installed in the containment sumps.
(3) Vent systems installed to permit reactor vessel and pressurizer venting.
The excess flow check valve installations in the CVCS' system were.noted to have been installed in accordance with the drawings. One exception involving the mislabeling of one valve was brought to the attention of startup Quality Assurance / Quality Control (QA/QC). No testing was required for this installation.
The temperature element installations in the containment sumps were noted to be incomplete. This was known by APS also. Only the temperature element portion have been installed. Control room instrumentation remains to be installed. The iristallation was designed as a Category 2 item as noted in Regulatory Guide 1.97, and the installation was not inspected by QC.
Exception was taken by the APS startup release group with respect to the installation fulfilling its design function. They noted that the installacion did not appear to prevent shorting of the circuit by sump fluid. This matter was brought to the attention of APS construction QA/QC who issued a corrective action report. The responsible engineer was aware that testing would be required however testing action will not be taken until that equipment is released'to startup from construction.
A review of the reactor vessel / pressurizer vent system confirmed completion ~
was incomplete. The viping system has been installed, however, power
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to valves and control room switches and pressure instrumentetion have not been installed.
It was noted that the two orifices installed in the lines in the proximity of the vessel head and pressurizer are sized as 7/32" x 1" as noted on drawings. The applicant's description in his TMI Lessons Learned comunication to'the NRC identified the size i
of these orifices (for LOCA consideration) to be 7/16"; This was brought to the attention of the applicant for resolution. Discussions with responsible test engineers confirme'd that they were aware that testing of the system would be required. Testing action is usually initiated when a system is released from construction.to'startup. This turnover had not been done as yet.
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No items of noncompliance or deviations were identified
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Preoperational Test Procedure Review The Structural Integrity Test procedure, which contains the test pressure sequence for both the SIT and the CILRT, was examined by the inspectors.
The procedure conformed to regulatory requirements and was consistent with
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administrative controls governing procedure development and approval. Minor typographical errors were brought to the. attention of personnel for correction.
Other procedures detailed in the following section were also examined.
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No items of noncompliance or deviations were identified.
Piping Verification Program The inspectors discussed with the principal startup engineer the ongoing preparations for the piping verif"ation program.
Some testing hcs commenced for steady state vibration and dynamic effects on the spent fuel pool cooling system. Testing on systems will commence whenever the syst a preoperational test for which piping verification testing is required are to be done.
The following test procedures were examined by the' inspectors for technical content, conformance to regulatory requirements, and consistency with administrative controls governing procedure development and apprcval:
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73TI-9ZZ03 - Snubber Preservice Examination Procedure.
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91HF-1ZZ07 - BOP Piping Dynamic Transient Test c.
91HF-1ZZ06 - 80P Piping Steady State Vibration Test d.
91HF-1ZZ08 - B0P Piping Thermal Expansion Test No items of noncompliance or deviations were identified.
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Startup Testing Selected tests of containment penetrations for local leak rate testing were observed by the inspectors. The inspectors verified that affected systems were properly tagged, test prerequisites were satisfied, and qualified personnel
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were performing the test activity. The testing has revealed.that a significant proportion of the valves being tested are not passing the first test. Following repair or replacement the valves subsequently have passed the tests.
The CILRT, which is a milestone test, is scheduled to convence December 17, 1982, and is on schedule. The inspector examined the equipment that has been installed for the conduct of the test. The pressurization skid has been brought into place, and has the requisite equipment installed por the applicable standards and codes. At present, the containment has been put on limited access to control the number of personnel and the work activity ~
in the containment that could possibly affect the test.
Pressurization will commence on the evening of December 17, after a walkdown of the containment is conducted.
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Insulation resistance testi',9 (Meggering) has been discontinued by the startup prerequisite group. The inspectors discussed this action with Region V.
personnel and will be following up in future inspections.
No items of noncompliance or deviations were identified.
6.
Preoperational Test Procedure Verification The inspectors verified that the applicant's program for precore and postcore hot functional tests includes those tests required per Chapter 14 of the CESSAR and the facility FSAR. This was done by comparing the applicant's Management Action Control - Status Report with the list of required procedures'.
The Mc;agement Action Control document lists all procedures as to their status, this includes those to be written and developed.
No items of noncompliance or deviations were identified.
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Tours Several plant tours have been conducted tj the inspectors during the period.
ine containment building has received a thorough cleanup in preparatiore for the Containment Integrated Leak Rate Test. Due'to several rainstorms, the facility has experienced a considerable amount of mud and dirt being tracked into spaces adjacent to building exits. This condition has abated somewhat but has posed problems in maintaining cleanness in the facility.
A selection of temporary modification log entries were examined by' the inspectors to verify that administrative procedures and controls over temporary modifications are being adhered to. The control room log.was examined regularly by the inspectors to confirm that the log is being maintained and contains entries of manipulations and notations of information essential to oncoming shifts.
The shift supervisor's log and the shift test coordinators log were also-examined.
No items of noncompliance or deviations were identified.-
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Exit Meeting The inspectors met with the Manager of Nuclear Operations and his staff on December 15, 1982 to summarize the findings of the inspectors.
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