IR 05000280/1979046
| ML18136A060 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/27/1979 |
| From: | Burke D, Kellogg P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18136A059 | List: |
| References | |
| 50-280-79-46, 50-281-79-65, NUDOCS 7910160347 | |
| Download: ML18136A060 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 AUG 2 7 1979 Report Nos. 50-280/79-46 and 50-281/79-65 Licensee: Virginia Electric and Power Company Richmond, Virginia 23261 Facility Name:
Surry Units 1 and 2 Docket Nos. 50-280 and 50-281 License Nos. DPR-32 and DPR-37 SUMMARY Inspection on July 9 - August 10, 1979 Areas Inspected This routine inspection by the resident inspector involved 98 inspector-hours
- onsite in the areas of plant operations and maintenance, including the Unit 2 steam generator replacement outage work, and followup on LER's and previously identified item Results Of the four areas inspected, no apparent items of noncompliance or deviations were identifie ~10160 5~
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DETAILS Persons Contacted Licensee Employees Virginia Electric and Power Company (VEPCO)
- W. L. Stewart, Station Manager
- J. L. Wilson, Superintendent, Operations
- T. A. Peebles, Superintendent, Technical Services
- R. F. Saunders, *Superintendent, Maintenanc;e R. M. Smith, Supervisor, Health Physics R. L. Baldwin, Supervisor, Administrative Services G.. Kane, Operating Supervisor
- F. L. Rentz, Resident QC Engineer
- D. A. Christian, Engineering Supervisor Other licensee employees contacted during this inspection included control room operators, shift supervisor, QC, engineering, HP, plant maintenance, security, eng~neering, and administrative personne *Attended exit intervie Management Interviews The scope and findings were summarized on a weekly basis with those persons indicated in Paragraph 1 abov.
Licensee Action on Previous Inspection Findings Not inspecte.
Unresolved Items Unresolved items were not identified during this inspection Unit 2 Steam Generator Replacement Activities The inspector reviewed certain U-2 SG replacement and associated activities to verify that the activities were performed in accordance with the Steam Generator Repair Program (SGRP) and applicable procedure The review included the following activities: Inspection tours of the Unit 2 containment for cleanliness and radiation control; appropriate work and radiation controls were being implemente * Followup on the thunderous arcing of the SOOKV line insulator over the backfed 2 B main transformer on July 9, 1979. The licensee performed
-2-testing to verify no transformer damage occurred *and repaired the standoff insulato Review of certain contractor and plant personnel records such as radiation exposure histories and time-cards to verify that exposures and worktimes were appropriately controlle Within the areas inspected, no items of noncompliance were identifie.
Review of Reportable Occurences The inspector reviewed the Reportable Occurence (RO) reports listed below to ascertain that NRC reporting requirements were being met and to determine the appropriateness of corrective action taken and planned. Certain Licensee Event Reports (LER) were reviewed in greater detail to verify corrective action and determine compliance with the Technical Specifications and other regulatory requirement The review included examination of log books, internal correspondence and records, review of SNSOC meeting minutes, and discussions with various staff member Within the areas inspected, no items of noncompliance or deviations were identifie LER 280/79-07 concerned an inoperable snubber due to low fluid level in the reservoir which had a fitting lea The snubber was rebuilt and retested. All snubbers will be inspected for operability prior to unit startup. This LER is close LER 280/79-11 addressed the temporary loss of power to the plant ventilation radiation monitors due to a loose connection on the power supply lead to the RM cabinet. The ventilation sampling system, which remained operable, maintained accountability during the even No significant releases were note The licensee stated that the cause codes would be corrected on a supplemental LE LER 280/79-12 addressed the special functional test of 74 snubbers performed during shutdown as a result of Unit 2 snubber testing and failure analysi of the 74 snubbers tested did not meet the acceptance criteria. The licensee is reviewing the data to determine the cause of the bleed and lockup rate drif The remainder of the testable snubbers were rebuilt and/or functionally tested in mid 1978, and a random sample of 10 of these snubbers was functionally tested on August 1, 1979 with no failures occurrin The LER remains open pending licensee review of the snubber setpoint drift and stress evaluation of the piping; the the inoperable snubbers have been repaired, retested, and reinstalled in Unit LER 280/79-13 concerned the inadvertent release of some 100 gallons of water from the boron recovery test tank 2B to the discharge canal ~**
-3-without prior samplin The event was caused by an improper valve lineup for recirculation in preparation for samplin The personnel involved have been reinstructed and discharge procedure OP 10.4 revised to ensure appropriate valve lineu Subsequent sampling indicated that the radioactive discharge was 0.6% of the limits specified in 10 CFR 20. This LER is close LER 280/79-14 addressed the high alarm setpoint drift on the liquid waste disposal radiation monitor (RM-LW-108).
Although the Technical Specification limit of 1.5 x 10-3 µCi/cc could have been temporarily exceeded, licensee analysis determined that the 10 CFR 20 limits were not exceeded. The LER is close LER 280/79-15 concerned liquid waste releases which contained isot~~e activity summatious that exceeded the TS 3.7.E limit of 1.5 x 10 uCi/cc; 10 CFR 20 limits were not exceede HP procedure 3.5.1 was revised to include additional administrative controls over liquid releases activities, since the radiation monitor can only be cali-brated to one isotope. This LER is close LER 280/79-17 addressed the potential for insufficient oil pressure to the emergency diesel generator turbocharger thrust bearing under certain restart conditions (eg -
several restarts after full load operation).
The licensee determined that the restrictive conditions have not occurred at Surry. The inspector verified that the D/G test procedures were revised to ensure that the above conditions would not occur during diesel startup or testin The manufacturer is evalua-ting the development of an improved lubricating oil system and will notify the licensee of progress. This *LER is close LER 280/79-19 concerned the failure of motor operated containment purge isolation valve 100D during shutdow The redundant isolation valve was operable. The failed bearing was replaced and the valve was satisfactorily tested after maintenance. This LER is close LER 281/79-10 concerned the failure of 19 out of 30 snubbers tested to meet the acceptance criteria for bleed and lockup in PT 39.2 (Snubber Functional Test).
The licensee is rebuilding or functionally testing every Unit 2 snubber. This LER remains open pending completion of the program and evaluation. (See LER 280/79-12 above).
Unit 1 Operations and Maintenance Surry Unit 1 remains shutdown following the issurance of the NRC Order to Show Cause concerning the piping stress analyses deficiencies; modifica-tions to the piping support systems are in progress. The inspector observed certain support installation work on the RlIR system inside Unit 1 containmen The anchor bolt and support installations were being performed in accordance with Design Change 79-S32 procedures, and appropriate HP monitoring was establishe However, the inspector did observe one inverted snubber, RH-HSS-11, in the work area on which the locknut was loose. The license
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-4-stated that the snubber will be replaced or purged and functionally tested; a 100% visual snubber inspection will be performed prior to startup. The inspector also toured the control room and certain Unit,1 plant areas to verify that the shutdown operations were in accordance with the Technical Specifications and facility procedure Plant logs and records were also reviewe Within the areas inspected, no items of noncompliance were identified. Specific areas of inspection included: Followup on the boric acid filter radiation levels (open item 280/79-31-01). Filter changeout reduced* the radiation levels in the immediate area by some SO%, and the licensee is continuing the radiation surveys and evaluatio Some radiation exposures (300 mr/individual max.)
occurred during the filter changeou Some deterioration of the Cuno filter material was also noted and is being evaluate This item remains open pending the results of the evaluation Review of recent periodic tests (PT 26.1 and 26.2) on the radiation monitors (RM) as part of the followup of the LER's discussed in paragraph 6 abov The inspector noted that certain RMs such as RM-LW-108 (liquid waste) and RM-CC-105 and 106 (component cooling water) did not respond to the daily source check because of the relatively high count rate on the channel. The licensee stated that shielding, decontamination, and relocation of RM detector RM-LW-108 is planned to reduce the background radiation levels, and stated that Design Change 77-29 (Relocation of RM-LW-108) will be reviewed prior to implementatio The licensee verifies instrument radiation level movement and operability _
if the instruments do not respond to the daily source response chec The licensee is also reviewing the monthly RM periodic test (PT 26.2)
to determine if a more integrated test could be performed on the instrumentation This item remains open pending licensee review and design change implementation (280/79-46-01). Review of certain maintenance and periodic test (PT) procedures to verify that the systems tested are returned to operable status at the completion of the tests. The inspector noted that step 5.1 of PT-18.1,
"Low Head SI Test", instructs the operator to close MOV-1862 A and B, which isolate the LHSI suction lines from the RWST, and then reopen the valves to verify operabilit The licensee is reviewing PT-1 to assure that the parallel valves are cycled individually. This item is open pending PT-18.1 review and/or revision or implementation of the revised PT program under ASME Section XI (280/79-46-02). Review, during conduct of the sessions, of a simulator and lecture retraining session for plant personne Verification that facility control rooms were staffed -in accordance with Technical Specification Observation of the high potential testing on the buried reserve station service cables (ST-63).
The license is investigating the apparent degradation of the Unit 2 cabling identified during testin J *
-5-Plant Physical Protection The inspector verified the following by observation: Gates and doors in protected and vital area barriers were closed and locked when not attende Isolation zones described in the physical security plans were not compromised or obstructe Personnel were properly identified, searched, authorized, badged and escorted as necessary for plant access control.