IR 05000302/1975011
| ML19317G382 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/12/1975 |
| From: | Robert Lewis, Rodgers R, Whitt K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19317G380 | List: |
| References | |
| 50-302-75-11, NUDOCS 8003030789 | |
| Download: ML19317G382 (9) | |
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UNITED STATES Cg NUCLEAR REGULATORY COMMISSION I
REGloN41 230 PEACHTREE STREET. N. W. SUITE SIS
ATLANTA, GEORGI A 30303 r
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IE Inspection Report No. 50-302/75-11 Licensee: Florida Power Corporation
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320134th Street, South P. O. Box 14042 St. Petersburg, Florida 33733
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Facility Name: Crystal River 3
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Docket No.:
50-302 License No.:
CPPR-51 Category:
B1
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Location: Crystal River, Florida Type of License: B&W, PWR, 2452 Mwt Type of Inspection: Routine, Unannounced Dates of Inspection: August 26-29, 1975 Dates of Previous Inspection: August 6-8, 1975 N.
Principal Inspector:
K. W. Whitt, Reactor Inspector Facilities Section Facilities Test and Startup Branch Accompanying Inspector:
R. F. Rogers, Reactor Inspector Engineering Section Facilities Test and Startup Branch Other Accompe-ing Personnel: None Principal Inspector:
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K. W. Whitt, Reactor Inspector Date Facilities Section Facilities Test and Startup Branch d M-
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Reviewed By:
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.R. C. Lewis, Senior Reactor Inspector Date Facilities Section Facilities Test and Startup Branch p *"*%,
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IE Rpt. No. 50-302/75-11-2 -
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SUMMARY OF FINDINGS
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I.
Enforcement Matters There were no items of noncompliance identified during the inspection.
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II.
Licensee Action on Previously Identified Enforcement Matters
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There were no previously identified enforcement matters requiring
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resolution.
III. New Unresolved Items None IV.
Status of Previously Identified Unresolved Items 75-4/1 Design Change Control Corrective action has been completed for discrepancies that were identified in the program for handling design O
changes during the test phase. This item is closed.
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(Details I, paragraph 2)
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75-4/2 ' Improper Machining of Pistons in Colt Industries (Fairbanks-Morse) Diesel Generators (ROB 74-16)
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The inspection and evaluation of the potential problem in the machining of diesel generator pistons has been completed. No discrepancies were identified.
This item is closed.
(Details I, paragraph 3)
75-4/4 Preoperational Test Procedure Resiew Comments resulting from the review of preoperational test procedures have been resolved.
This item is closed.
(Details I, paragraph 4.a)
75-8/1 Preoperational Test Results
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Comments resulting from the review of the results of two tests have been resolved.
This item is closed.
0 Details I, paragraph 5)
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75-8/2 Preoperational Test Procedure Review
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One general comment which resulted from the review of preoperational test procedures has not been
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resolved. This item remains open.
(Details I, paragraph 4.b)'
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V.
Unusual Occurrences
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None
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VI.
Other Significant Findings
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A.
Project Status The fuel load date has been advanced from May to March 1976.
The licensee reported that Construction is 95% complete and approximately 41% of the overall test program has been completed.
In order to support the new fuel load date, the following key test start dates have been tentatively established:
1.
Primary System Hydrostatic Test - October 5,1975 2.
Containment Leak Rate Test - December 4,1975 3.
Hot Functional Testing - December 18, 1975.
B.
Organizational Changes 1.
The project manager organization has been finalized.
The Project Manager reports to the Senior Vice President, Systems Engineering and Operations. A project team has been appointed which will report to the Project Manager.
The team members represent the various functional areas presently active on site. Each member is the head of his respective function.
The functional areas are
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construction, testing, controller, operations, quality and environmental, data, and engineering.
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The Assistant Vice President, Quality and Environmental
and those departments reporting to this position now report to the Vice President and General Council. The assistant Vice President formerly reported to the Senior
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Vice President, Systems Engineering and Operations.
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IE Rpt. No. 50-302/75-11-4
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3.
The position of Plant Operations Supervisor is presently
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vacant due to the death of Mr. J. K. Jinkenson who had held the position for approximately one year.
C.
Performance Testing of the Sodium Thiosulfate Reactor Building
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Spray System-r A drawdown test is planned to determine the flow rate from the
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sodium thiosulfate and sodium hydroxide tanks relative to the
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flow rate from the borated water storage tank. This item
remains open.
(Details I, paragraph 6)
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D.
Defective Westinghouse Type OT-2 Control Switches (IEB 75-6)
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The licensee has indicated that the switches referenced in IEB 75-6 are not in use in safety related systems at Crystal
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River 3.
This item is closed.
(Details I, paragraph 8)
VII. Management Interview A management interview was held at the conclusion of the inspection on August 29, 1975. The findings of the inspection were discussed.
The following licensee _ personnel participated:
J. Alberdi - Project Manager E. E. Froats - Manager, Site Surveillance J. C. Hobbs, Jr. - Manager, Generation Testing R. W. Slater - Quality Engineer J
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IE Rpt. No.- 50-302/75-11 I-1
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DETAILS I Prepared by:
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K. W. Whitt, Reactor Inspector Date Facilities Section-Facilities Test and Startup Branch
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-Dates of Inspection: August 26-29, 1975 lL^
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Reviewed by:
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R. C. Lewis, Senior Reactor Inspector Date
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Facilities Section Facilities Test and Startup Branch
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1.
Individuals Contacted i
Florida Power Corporation (FPC)
J. Alberdi - Project Manager J. C. Clapp - Manager, Site Quality Surveillance Audits
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E. E. Froats - Manager, Site Surveillance
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J. C. Hobbs, Jr. - Manager, Generation Testing
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M. H. Kleinman - Director, Quality Programs D. A. Morrison, Jr. - Nuclear Operator C. R. Pope - Administrative Manager i
A. P. Vogt - Manager, Test Procedures R. W. Slater - Quality Engineer
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2.
Design Change Control
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This unresolved item (75-4/1) was identified in IE Report No.
50-302/75-4, Details I, paragraph 3, and subsequently discussed in IE Report No. 50-302/75-8, Details I, paragraph 4.
The revision of the-quality assurance manual (QAM) has been completed.
Quality Procedure (QP) 3.11, " Design Change Control," requires the Director, Generation Engineering, to coordinate with and receive
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approval from the architect engineer for safety related design changes or design changes involving changes to the FSAR. Where
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design changes involve changes to the nuclear steam supply system (NSSS), the NSSS vendor must also approve the change.
Quality program policy procedure (Policy) 3.1 states that during the design and construction phase (This phase. includes preoperational and startup testing), changes to the design require the same review and approval as the original design.
Engineering Department pro-cedures implement the QAM requirements.
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IE Rpt. No.-50-302/75-11 I-2
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When either the NSSS vendor'or the architect engineer determines that a change to'the FSAR is desirable, the FPC licensing group
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l is so informed. FPC then reviews and evaluates.the recommended change, and if they concur with the recommendation, an amendment
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to the FSAR is submitted to NRC. This item is closed.
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3.
Improper Machining of Pistons in Colt Industries (Fairbanks-Morse)
Diesel Generators (ROB 74-16)
o This unresolved item (74-4/2) was identified in IE Report No.
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50-302/75-4, Details I, paragraph 7, and subsequently discussed r
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in IE Report No. 50-302/75-8, Details I, paragraph 5.
The in-
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spection of the diesel generators has been completed. The results s
of the inspection indicate that all pistons in both generators had
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been' properly machined. This item is closed.
4.
Preoperational Tesc Procedure Review
Unresolved Item 75-4/4 a.
This unresolved item was identified in IE Report No. 50-302/75-4, Details II, paragraph 2, and subsequently discussed in IE Report No. 50-302/75-8, Details I, paragraph 7.
Action to resolve the comments which retulted from the review of fifteen preoperational test procedures has been completed. The inspector reviewed the corrective action during this inspection and has I
no further questions. This item is closed.
b.
Unresolved Item 75-8/2 i
This unresolved item was identified in IE Report No. 50-302/75-8,
Details II, paragraph 2.
Two general comments and six specific comments resulted from the review of three preoperational test procedures. All the comments except one had been resolved at
the conclusion of this inspection and the action taken by the
I licensee was reviewed during the inspection. The following general comment will remain outstanding:
There are no provisions to prevent safeguards systems pump runout either by use of valve throttling or flow ~ restricting
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orifices that would provide protection against pump trips
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A licensee representative stated that this condition was being
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evaluated.
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Preoperational Test Results Review
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This unresolved item was identified in IE Report No. 50-302/75-8, Details I, paragraph 2.
These comments involving changes to test procedures resulted from the review of the results of two tests.
Corrective action to resolve these comments has been taken through
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inter-office correspondence dated July 28, ?975, from the manager, generation testing, to all testing superia 2 dents.
This correspondence contains the following instructions:
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Continue to sequentially number and date minor and major changes
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a.
- to test procedures (TP) in the text of the TP, and when listing major or minor changes on the GT-41 form, follow the same numbering sequence and be certain to list the date of each change on GT-41.
b.
Class I and II minor changes to TP's must be written and submitted on GT-41 forms so that approval of the test working group (TWG) and manager, generation testing is obtained as soon as possible but in no case later than 14 days after implementation.
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Testing quality control will audit, regularly, the GT-41 forms to determine if trends or other problems exist in the manner or extent of changes implemented in TP's.
The audit reports are to be submitted to the manager, generation testing.
This item is closed.
6.
Possible Deficiency In The Performance of The Sodium Thiosulfate Reactor Building Spray System
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This item was identified in IE Report No. 50-302/75-8, Details II, paragraph 4.
FPC plans to conduct a drawdown test to determine whether the sodium thiosulfate and sodium hydroxide systems function as designed.
The borated water storage tank, the sodium thiosulfate tank and the sodium hydroxide tank will be filled with water and then all trains of the low pressure injection system, high pressure injection system and containment spray system will be started to pump the water from the three tarks to the refueling canal.
l The relative levels of the tanks will be recorded and evaluated as appropriate.
The procedure to be followed for this test is presently I
in draft form.
The test is echeduled to be performed during the week of September 8, 1975.
This item will remain open until the test has been conducted and the test results have been evaluated.
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IE Rpt. No. 50-302/75-11 I-4
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Verification of Review and Approval of Category II Test Procedures
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Category II test procedures were reviewed on a sample basis to deter-mine whether adequate testing is planned to satisfy regulatory guidance
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and licensee commitments.
No discrepancies were identified during the review of approved procedures.
However, approximately 30% of the procedures inspected had not been approved. The procedures that
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remain to be reviewed are:
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a.
TP 7 2 210 07, " Chemical Addition and Sampling System Hydro Test"
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b.
TP 7 2 210 02, " Chemical Addition and Sampling System Electrical Test"
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TP 7 2 210 03, " Chemical Addition and Sampling System Electrical Test" d.
TP 7 2 320 01, "ICS Preoperational Calibration"
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TP 7 2 320 02, "ICS Open Loop Calibration"
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TP 7 2 330 01, "CRD Control System Preoperational Calibration" g.
TP 7 2 330 02, "CRD Control System Operational Test" h.
TP 7 2 330 03, "CRD Mechanism Functional Test" 1.
TP 7 2 330 04, "CRD Integrated Test" I
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TP 7 2 330 05, "CRD Trip Test" i
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TP 7 2 452 01, " Communications System Electrical Test" 1.
TP 7 2 452 02, " Communications System Functional Test" 8.
Defective Westinghouse Type OT-2 control Switches (IEB 75-6)
FPC has advised Region II by letter dated June 17, 1975, that no Westinghouse Type OT-2 electrical switches are in use or planned for future use in safety related systems at Crystal River 3.
This item is closed.
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'~'T IE Rpt. No.-50-302/75-11 II-l
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DETAILS II Prepared by:
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i-R. F. Rogers,'Reacdbr Inspector
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Nuclear Engineering.Section
Facilities Test and Startup Branch
Dates of Inspe tion:
, gust 26-29, 1975
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Reviewed by:
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H. C. Dance, Senior Reactor Inspector Datd
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Nuclear Engineering Section
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Facilities Test and Startup Branch
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Personnel Contacted R. Slater - Quality Engineer
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C. Pope - Administrative Manager J. Hobbs - Manager Generation Testing 2.
Review of Preoperational Test Program A review was conducted of 68 of the approximately 200 Class I and
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Class III test procedures to determine compliance with Regulatory
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Guide 1.68 and FSAR Section 13.2.5.
Tests were selected to be repre-
sentative of the total scope of the test program.
For the selected
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tests, it was verified that a procedure existed which e,.9 properly
reviewed and approved by plant personnel.
Approximately one-third of the procedures selected had not yet been approved for use.
These
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procedures will be inspected when approved.
3.
Review of Preoperational Test Procedures The following procedures were reviewed for consistency with the require-i ments of Regulatory Guide 1.68 Appendix C," Preparation of Procedures" and FSAR Table 13-1,"Prefueling Test Summary." The inspector had no
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further comment on these tests.
- TP 71 200 04 Reactor Coolant System Hydro TP 71 600 05 Chemical Addition and Sampling System Operational Test
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TP 71 600 14 Pipe and Component Hanger Hot Inspection Test
TP 71 310 03 ES Detection and Actuation Test.
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Review of Preoperational Test Results Evaluation
The inspector attempted to review selected procedures to assure that the
licensee was performing an adequate evaluation of test results; however, only 17'of the approximately 325 preoperational tests have been reviewed
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by the plant staff. None-of the procedures selected had yet-been reviewed.
This area will be deferred to a subsequent _ inspection.
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