IR 05000302/1976012
| ML19308D250 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/15/1976 |
| From: | Jape F, Robert Lewis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19308D125 | List: |
| References | |
| 50-302-76-12, NUDOCS 8002270703 | |
| Download: ML19308D250 (6) | |
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UNITED STATES j
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,1 NUCLEAR REGULATORY COMMISSION
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IE Inspection Report No. 50-302/76-12 Licensee: Florida Power Corporation 320134th Street, South P. O. Box 14042 S t.
Petersburg, Florida 33733
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Facility Name:
Crystal River 3 Docket No.:
50-302 License No.:
CPPR-51 Category:
B1 Location: Crystal River, Florida Type of License: B&W, PWR, 2452, Mut Type of Inspection: Routine, Announced O
Dates of Inspection: June 28 - July 2, 1976 Dates of Previous Inspection: June 15-18, 1976 Inspectors:
F. Jape Reactor Inspector Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Accompanying Inspectors: None Other Accompanying Personnel: None Principal Inspector:
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- W F. Jape, Reactor Ipspector Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch
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Reviewed By:
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R. C. Lewis, Chief Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch l
8002270 2 0 3
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IE Rpt. No. 50-302/76-12-2-
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SUMMARY OF FINDINGS I.
Enforcement Matters None II.
Licensee Action on Previously Identified Enforcement Matters Not inspected.
III. New Unresolved Items None IV.
Status of Previously Identified Unresolved Items i
75-8/3 Operability of Category I Hydraulic Shock and Sway Suppressors (IEB 75-05)
Suppressor inspection currently in progress during HFT.
Item remains open pending completion of inspection re-quirements.
(Details, paragraph 3.a)
V.
Unusual Occurrences None i
VI.
Other Significant Finding None VII. Management Interview A management interview was held on July 2, 1976, with J. Alberdi, and members of his staff. The inspection findings related to witnessing preoperational testing activities were discussed.
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IE Rpt. No. 50-302/76-12-1-DETAILS Prepared by:
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F. Jape, Reactor Inspector
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Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch
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Dates of Inspection: June 28-July 2, 1976
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Reviewed by: /
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R. C. Lewis, Chief
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Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch 1.
Individuals Contacted Florida Power Corporation (FPC)
E. E. Froats - Manager, Site Surveillance R. A. Parker - Chief Nuclear Operator
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W. W. Surrency - Chief Nuclear Operator
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T. N. Mount - Nuclear Operator
G. P. Hebb - Assistant Nuclear Operator J. F. Heilman - Assistant Nuclear Operator R. N. Stuart - Assistant Nuclear Operator W. E. Kemper - Assistant Nuclear Operator W. M. Mathews - Shift Supervisor W. R. Nichols - Operations Supervisor H. J. Eck - Chemistry / Radiation Technician J. R. Wright - Chemistry / Radiation Protection Engineer J. C. Hobbs, Jr. - Manager, Generation Testing A. P. Vogt - Testing Superintendent J. A. Jones, Inc. (JAJ)
J. Shively - Calibration Technician Babcock & Wilcox, Inc. (B&W)
J. J. Kelley - Shift Testing Superintendent J. R. Bohart - Startup Test Engineer W. R. Jacobs'--Startup Test Engineer NUS B. Seaholts - Testing Engineer (N)
J. H. Greene - Startup Test Engineer
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IE kpt. Ms. 50-302 76-12-2-s
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W. Mathis - System Test Engineer T. Phelps - System Test Engineer
E. T. Childress - Startup Test Engineer i
2.
Witness of Integrated Hot Functional Testing The inspector witnessed a portion of test proceduro TP 716000,
" Hot Functional Testing." The primary coolant system was at a nominal 532 F and 2155 psig during periods of inspector observation.
In general, the inspector verified that the proper procedures were in use, test prerequisites were met, the required systems to support the ongoing testing were placed in service as prescribed by procedures, crew actions were timely, attentive and responsive, and the records-being maintained were as prescribed by the test program guide.
Discussions with operators and testing personnel revealed that they were using the current revision of the procedure. The operators at the I
control panels in the control room and those in charge of operating equipment in other locations throughout the plant were observed to
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i be attentive and responsive.
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The chronological log was reviewed and found to contain detailed information concerning the conduct of testing.
Log entries concerning
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the ongoing testing were found to be complete. The inspector had no adverse comments or questions regarding this record.
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Witness of Preoperational Testing
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Portions of the following tests were witnessed by the inspector.
The performance of each test was evaluated against the requirements of ANSI N18.7 - 1972, Rev.1, Section 5.3.10, " Test and Inspection Procedures," ANSI N45.2 - 1971 Section 12, " Test Control," and FSAR Chapter 13, " Initial Tests and Operations." There were no discrepencies identified by this inspector.
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TP 600-14, " Pipe and Component Hanger Hot Instection Test"
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i The inspector observed licensee personnel recording measurements for pipe hangers and suppressors in the reactor building at normal
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operating pressure and temperature.
In general,.these data appeared to agree with prescribed values. At least one suppressor
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was observed to be out-of-service due to its physical arrangement.
A change request for rearranging this suppressor has been O
instituted.
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IE Rp t. No. 50-302/76-12-3-
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Licensee personnel were also observed making measurements of high energy lines and auxiliary piping in the auxiliary and turbine buildings. Sections of the feedwater lines were observed to be vibrating and had been lashed down with cables. Permanent hangers are planned to be installed for these lines following cooldown.
Measurements and data obtained for PT 600-14 also fulfill the licensee's commitments to IEB 75-05, "Operabilit; of Category I Hydraulic Shock and Sway Suppressors." The required surveillance procedures for periodic inspection of snubbers and restraints have not been issued. This - subject has been previously identified as unresolved item 75-8/3. The unresolved item will remain open pending issuance of an acceptable surveillance procedure and review and acceptance of data from TP 600-14.
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TP 330-3, "CDR Functional Test," and TP 600-17, "CDR Operational-b.
Test" The inspector observed the final portion of TP 330-3 being run.
Each rod was operated individually during this test and accuracy of position indicators (PI) were verified. The 12 PI tubes
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reported defective in IE Report 50-302/76-7 have been repaired and rechecked. At the completion of this test all PI tubes were operational.
Y; objective of TP 600-17 was to operate the rod system in its normal configuration while checking the asymmetric fault
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indication, group position indication and sequence monitors.
The inspector witnessed the initial part of this procedure.
A major change to the procedure was made prior to initiating the test.
The change was processed as prescribed by Test Program Guide 1.1, Section 2.7.1.1.
The change involved clarification of acceptance criteria.
The inspector also verified the initial test conditions were as required by the procedure.
TP 600-23, "RPS Functional Test" c.
Checkoat of portions of the reactor protective system (RPS) was Features such as system logic, channel witnessed by the inspector.
. bypass key switch, shutdown bypa a key switch, loss of vital bus power source and simulated trip conditions for the protective functions ware verified. The system performed as described in Section 7.1 of the FSAR.
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IE Rpt..No. 50-302/76-12-4-
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TP 600-3, " Soluble Poison Concentration Control"
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The ability to adjust boron concentration in the reactor coolant system was witnessed by the inspector.
In addition, the laboratory technique for analyzing boron concentration was observed.
TP 600-12, " Pressurizer Test" e.
The portion of this test which dealt with checking and resetting the pressurizer relief valves at operating temperature was witnessed.
RCV-8F required resetting since on initial check the popping pressure was out-of-allowable tolerance. The valve was reset and retested in place, by using a hydroset.
The calibration records for the test gauge and hydro pump used for performing these tests were in conformance with the requirements of Generation Test Procedure 1.3.
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