IR 05000280/1986024
| ML18149A338 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/02/1986 |
| From: | Jape F, Larry Nicholson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18149A336 | List: |
| References | |
| 50-280-86-24, 50-281-86-24, NUDOCS 8610150071 | |
| Download: ML18149A338 (4) | |
Text
Report Nos.:
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30323 50-280/86-24 and 50-281/86-24 Licensee:
Virginia Electric and Power Company Richmond, VA 23261 Docket Nos.:
50-280 and 50-281 Facility Name:
Surry 1 and 2 License Nos.:
DPR-32 and DPR-37 Inspection Con,cted:. September 8-12, 1986 Inspector: Lf? ;1/;£?...J--
L. E. Nicholson Approved by: 4f.1e.~-1~ *
F.ape,Section Chief Engineering Branch Division of Reactor Safety SUMMARY ii[) eSi gned
/olz/F6 Date Signed Scope:
This routine, unannounced inspection was in the areas of surveillance testing and dry spent fuel storag Results:
No violations or deviations were identified.
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PDR A, 7 1 861003*
G Docx 05000280 PDF? Persons Contacted Licensee Employees REPORT DETAILS R. H. Blount, Supervisor, Performance Engineering
- W. P. Grady, Supervisor, Quality Assurance
- E. S. Grecheck, Superintendent, Technical Services
- H. L. Miller, Assistant Station Manager J. Rayno, Performance Engineer
- R. F. Saunders, Station Manager Other licensee employees contacted included engineers, technicians, operators, and office personne NRC Resident Inspector
- W. E. Holland, Senior Resident Inspector
- Attended exit interview Exit Interview The inspection scope and findings were summarized on September 12, 1986, with those persons indicated in paragraph 1 abov The inspector described the areas inspected and discussed in detail the inspection finding No dissenting comments were received from the licensee. The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspectio.
Licensee Action on Previous Enforcement Matters (Closed)
Violation 280, 281/86-05-01, which concerns performing surveillance testing within the Technical Specification required schedule and the proper: documentation and evaluation of the test result The inspector reviewed in detail the system implemented to schedule periodic tests as defined in Administrative Procedure 89, Test Contra A comp uteri zed Periodic Test tracking system has been modified to include all those tests which have fixed frequency test intervals. This tracking system also provides a method for notifying management of the tests required during a month, with those noted that are overdu The inspector al so reviewed Engineering Procedure 39 which provides specific instructions regarding scheduling, performance and review of tests without fixed intervals (i.e., refueling and cold shutdown tests).
Responsibility for coordinating the surveillance tests has been shifted from the various departments responsible for performing the test to a central Survei 11 ance and Test Grou This group al so performs an independent second review of completed tests to assure that tests have been properly completed in accordance with station procedures. Based on the satisfactory implementation of the above corrective action, this item is close (Open)
Unresolved Item 280, 281/85-39-01 regarding temperature compensation for setpoint testing of pressurizer safety valve The licensee in conjunction with Wyle Laboratories performed extensive testing of the three Unit 1 Crosby pressurizer safety valves, serial numbers SV-1551A, SV-1551B, and SV-1551 The results of this testing is documented in Wyl e Report No. 48332-0 which indicates that an increased system temperature does effect the setpoi nt at which the valve would actuat Testing was performed using both nitrogen and stea The inspector expressed concern regarding incorporation of a fixed correction factor for each valve during further testing as prescribed in Station Cammi tment Response Form 86-5032-00 Testing performed at Wyle supports the conclusion given in Electric Power
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Research Institute (EPRI) Report NP-4235 that a correction factor would be difficult to achieve due to variance in test result The licensee concurred with this concern and further stated that permanent corrective action is still being formulate This item will remain ope.
Unresolved Items Unresolved items were not identified during the inspectio.
Surveillance Testing (61700) The inspector reviewed the completed surveillance tests performed by the operations group for Unit 1 during the month of July. This review included the following test procedures:
PT 10. 0 PT 15.18 PT 2 PT 3 PT 3 Reactor Coolant Leakage Steam Generator Auxiliary Feed Pump Radiation Monitoring Equipment Check Reactor Power Calibration Using Feed Flow Instrument Surveillance These tests were reviewed to verify the following:
Test results were adequately evaluated Proper review, evaluation, and acceptance of test results were accomplished Acceptance criteria was met
Tests were performed within the time frequencies specified by the Technical Specification The inspector witnessed testing per PT 5.1, Individual Rod Position Indicatio This test verifies the proper indication of each control rod position with the activation of appropriate alarms and annunicators at prescribed positions. The following attributes were verified during this review:
Tests were performed in accordance with approved procedure Test equipment required by the procedures was calibrated and installe Test data were properly collected and recorde Adequate coordination existed among personnel involved in the tes Test prerequisites were me Problems encountered during testing were properly documente Within the areas inspected, no violations or deviations were identifie.
Dry Spent Fuel Facility (37701)
The inspector toured the north bay and crane building to be used for dry spent fuel storage under Materials License No. SNM-250 This tour included an inspection of the pathway, associated equipment and cask to be used to transfer spent fuel from the containment, load the fuel into the cask, and prepare the cask for transporting to the storage pa The inspector also witnessed a 156 ton static load test of the independent spent fuel storage installation (ISFSI) crane for certification to handle the loaded cask Within the areas inspected, no violations or deviat1ons were identified.