IR 05000338/1979016
| ML19248C781 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/02/1979 |
| From: | Cantrell F, Webster E, Whitener H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19248C778 | List: |
| References | |
| 50-338-79-16, NUDOCS 7907050071 | |
| Download: ML19248C781 (7) | |
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UNITED STATES p, af oug
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Report Nos. 50-338/79-16 and 50-339/79-22 Licensee: Virginia Electric and Power Company P. O. Box 26666 Richmond, Virginia 23261 Facility Name: North Anna Units 1 and 2 Docket Nos. 50-338 and 50-339 InspectionatNorthAnna{ite..nearMineral, Virginia Inspectors:
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/, 'k7k E. H. Webster Date Signed h, / /,)f
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H. L. Whitener-'
y Da e ned Approved by:_ [- d
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FT S. Cantrell, Actinf'Section Chief, RONS Branch Date' Signed
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SUMMARY Inspection on April 2-4 and 4-5, 1979.
Areas Inspected This routine unannounced inspection involved 28 inspector-hours onsite in the areas of licensee event reports, followup of previously identified items, hydraulic snubber inspection, and review of the Startup Physics Report (Unit 1);
8 inspector-hours onsite in the area of comparison of as-built systems to FSAR (Unit 2).
Results Of the five areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees W. K. Cartwright, Station Manager
- J. D. Kellams, Superintendent - Station Operations
- D. L. Smith, Resident QC Engineer
- D. G. Mci.ain, Engineering Supervisor
- W. R. Madison, NRC Coordinator J. M. Mosticone, Jr., Shift Supervisor
- E. W. Harrell, Superintendent - Maintenance
- E. R. Smith, Superintendent - Technical Services
- H. W. Burruss, Engineer - Mechanical
- J. R. Eastwood, Mechanic A. Proffitt, Mechanic NRC Resident Inspector M. S. Kidd
- Attended ex.:t interview on April 4.
- Attended exit laterview on April 5.
2.
Exit Interview The inspection scope and findings were sammarized on April 4 and 5,1979, with those persons indicated in Paragraph I above. These findings are discussed in the details of this report.
3.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (338/79-04-01 and 339/79-06-01):
Establish that Viton seal material in the steam generator and reactor coolant pump snubbers is compatible with the environment. The inspector found that the licensee and Stone and Webster have reviewed the use of Viton A seal material and that this material is identified for use in snubbers inside containment in Supplement 5.73 of the FSAR (Amendment 57).
4.
Unresolved Items Unresolved items were not identified during this inspection.
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Licensee Event Reports Review (Unit 1)
The following IT.R's were reviewed to verify that reporting requirements had been met, causes had been identified, corrective actions appeared appropriate, generic applicability had been considered, and the LER forms were complete.
Additionally, for those reports identified by detailed review was performed to verify that the asterisk, a more licensee had reviewed the events, corrective actions had been taken, no unreviewed safety questions were involved, and violations of regula-tions or licensee / Technical Specification conditions had been identified.
LER 79-009/03L-0, Snubber support for "C" steam generator damaged.
a.
b.
LER 79-01C/03L-0, Particulate monitor RMS159 found out of calibra-tion.
LER 79-011/03L-0, Fire door S54-9 found to be non-functional.
c.
d.
LER 79-012/03L-0, Unidentified primary coolant leakage due to valve packing leakage.
LER 79-013/03L-0, Fire door S71-7 found to be non-functional.
e.
f.
LER 79-014/03L-0, Pressurizer level instrument found out of calibration.
g.
LER 79-015/03L-0, Control rod F08 position indication disagreement with demand position.
h.
LER 79-016/03L-0, Auxiliary feedwater pump 1-W-P-2 inoperable during steam valve repair.
i.
LER 79-017/01T-0*, Axial Power Distribution Monitoring System (APldS) FQ survey program inoperable. This program problem, in which constants were found to be in error, appeared to originate from a computer failure on January 24.
The licensee does not presently require constants to be reverified following a PRODAC-250 computer failure in procedure 1-AP-42, but verifies all constants at least monthly, and or whenever any constants are changed.
Licensee management has a computer program to verify constants and is changing procedure 1-AP-42 to include this verification after the computer is restored as indicated in the LER. The inspector will followup on this area when the procedure has been revised (338/79-16-01).
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LER 79-018/03L-0, Auxiliary feedwater pump 1-W-P-2 inoperable during steam valve repair.
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LER 79-019/03L-0, Emergency diesel 1H slow to develop rated speed during surveillance test.
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LER 79-020/03L-0, Fire door S54-9 found to be non-functional.
m.
LER 79-021/99T-0*, Meteorological delta temperature indication faile. *or nine days.
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LER '9-022/03L-0, Hydrogen recombines number 2-HC-HC-1 inoperable for.our hours due to electrical maintenance.
LER 79-023/03L-0, Control rod D-10 position indication disagreement o.
with demand position.
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LER 79-025/03L-0, Power range channel N42 tripped for maintenance.
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LER 79-027/03L-0, Axial flux difference outside 5% band during operations.
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LER 79-028/03L-0*, Control rod N-08 position indication disagree-ment with demand position. Due to the repetitive nature of this occurrence (see LERs 79-15 and 79-23) the licensee is conducting an engineering study of individual rod position indication voltage drift in the signal conditioring card. Licensee representatives explained that discussions with Westinghouse, the vendor, indicated that the design of this system may not be consistent with the 12 step Technical Specification limit placed on accur acy of the system.
The inspector will review final corrective actiens taken by the vendor or licensee in future incpections (338/79-16-02).
s.
LER 79-031/03L-0*, Three required surveillances overdue.
The inspector reviewed the licensees surveillance tracking system and discussed VEPC0 letter serial no.
142 dated March 13,1979, which requests relief from other surveillance requirements which are due prior to the 1979 refueling outage. The licensee appears to have complete listing of required surveillance including dates last a
completed.
However, since frequency for surveillance conduct is based on completion dates for preoperational tests, several sophis-ticated tests are due prior to the scheduled September refueling.
Since the three tests involved in the LER were not completed at the time of this inspection, they will be reviewed in future inspections (338/79-16-03).
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Open Itens a.
Hydra:ilic Shock Suppressors The inspector reviewed licenseee action on matters previously iden-tified for follow up review and inspected installed support and restraint systems inside the Unit I containment. The inspection findings are discussed below.
(1) Unresolved Item (338/79-04-01) and (339/79-06-01) - This item is considered resolved. For details, see paragraph 3.
(2) Open Item (338/79-02-01) - the licensee had identified 39 inaccessible and 16 accessible hydraulic shock suppressors for which the records indicated tests had been performed by the vendor but no data on the lock up and bleed rates was available.
The licensee had located data which indicated acceptable rates for 19 of the 39 inaccessible snubbers.
During the outage of April 1979 the licensee tested an additional four inaccessible snubbers (20% of those remaining without data verification) and found that these units met the lock up and bleed rate operating requirements as modified by a special Stone and Webster engineering evaluation of ther=al expansion rates for the involved systems.
This evaluation also indicated that the bleed rates obtained for a sample of seven accessible units tested on January 24, 1979 (see IE Report 50-338/79-04 and 50-339/79-06) were acceptab~e when compared with the analysed thermal expansion rates for the involved systems. At the exit interview the inspector indi-cated that this item is considered closed at this time based on the engineering evaluation by S&W, the record verification of 19 inaccessible units, and the functional testing of a sample of 4 inaccessible and 10 accessible units. The inspector advised the licensee that the remaining snubbers for which vendor tests were performed but no lock up and bleea. ate data available at this time, must be verified operable at the September 1979 refueling outage by identification of appro-priate documentation or by functional testing. The licensee agreed. Verification of the lock up and b!eed rate for the remair.ing 16 inaccessible and 6 accessible snubbers is iden-tified for inspector followup review as open item:
(50-338/
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79-16-04).
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(3) Open Item (339/79-06-03) - the licensee had committed to recheck snubbers and hangers at cold conditien for which deficiencies were noted and changes made during system heat up (see IE Report 339/ 79-0j). The inspector found that the licensee has established a computerized punchlist for deficient snubbers 90c q 't LU)
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Hcwever, an-tic.e did not permit an adequate review of identified defleien-cies, resolutions and/or modifications at this inspection.
This item will remain open for further review.
(4) NRC Position - the licensee was previously informed that the NRC considers an empty snubber reservoir a basis for declaring a snubber inoperable. The inspector found that the licenzee has inco rporated this position in Mechanical Maintenance Administrative Procedure 7 and has no further questions on this matter.
(5) Open Item (338/79-04-02 and 339/79-06-02) - the licensee has excluded "RC" designated snubbers f rom functional testing (PT-79.3).
The inspector informed the licensee that this matter is under NRC review and is still open.
b.
The inspector reviewed licensee action on other previously identi-fied NRC concerns. Of the four areas checked outside the realm of shock suppressors, only one had any significant development:
(0 pen) Open Item (338/78-42-06) Feedflow signal accuracy in the computer for use in conducting calorimetric measurements. The licensee has run a special test and is conducting an engineering study of the results to assure computer data accuracy is within calorimetric tolerances.
Results are expected within the next month.
7.
Review of Test Report (Unit 1)
The VEPCO report VEP-FRD-31, " North Anna Unit 1, Cycle 1 Startup Physics Test Report" was reviewed in detail in the Region II Of fice.
The results reported therein are consistent which preliminary data reviewed on site. cad reported on in inspection reports 338/78-11, 78-13 and 78-29. This report for North Anna 1 was also compared with the results reported for a similar facilities. All of the differences noted appeared to be within the uncertainties of the boron concentration determination from which the results were desired.
8.
Comparison of As-Built Systeut to FSAR (Unit 2)
The inspector compared system walkdown notes on applicable prints used in NRC inspection reports 339/79-13, 78-32, and 73-35 to FSAR drawings on systems as detailed below.
a.
FSAR figure 6.2-64 dated 11-3-78 details the number of spray nozzles on the quench spray, inside recirculation spray and outside recirculation spray systems. Th:ough review of as-built b b kf[Ek-
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the inspector verified the proper number of nozzles were installed on these systems.
(1) Quench Spray System is required to have 239 nozzles on each header per FSAR figure 6.2-64.
Prints 12050-QS-2423A Rev. O and 12050-QS-2422A Rev. O verified the proper number of unplugged nozzles were installed.
(2) Outside Recirculation Spray is required to have 360 nozzles per 180 degree header per FSAR figure 6.2-64.
Prints 12050-RS-2429A Rev. O and 12050-RS-2422A Rev. O and E&DCR P2296A -?
verified the proper number of unplugged nozzles were installed.
(3)
Inside Recirculation Spray is required to have 150 nozzles per 180 header per FSAR figure 6.2-64.
Prints 12050-RS-2420A Rev. O and 12050-RS-2421A Rev. O verified the capacity to install at least this number of nozzles. The inspector was unable to review E&DCR P2145 to verify that directions for nozzle plugging resulted in the proper number of operable nozzles. This area will be reviewed in future inspections.
b.
Safety Injection System The system was walkej-down using prints 12050-FM-96A-8 and 12050-FM-96B-7 as reported in IE Report 339/79-13.
These prints were compared to FSAR figures 6.3-1 and 6.3-2 both dated November 3, 1978, respectively.
(1) Twenty-four vent, drain or sample prints were found to either be missing or misplaced on the FSAR figure from the prints (339/79-22-01).
(2) The isolation and drain valve locations for the recirculation lines to the hot and cold legs dif fered between the print and FSAR figure 6.3-2.
As indicated in Report 339/79-13 paragraph 5d, the drain valves and isolation valves are actually oriented dif f erently from the print as well (339/79-22-02).
(3) The nitrogen supply tap off to PCV 2455C and PCV 2456 on print 12050-FM-960-7 is not on FSAR figure 6.3-2 (339/79-22-03).
(4) Three other appareht errors in the FSAR in valve locations on figure 6.3-1 were also noted (339/79-22-04).
All items indicated above were detailed to a licensee representa-tive for resolution and will be followed up on future inspections.
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Residual Hea3_R;goval System The system was walked-down using print 12050-FM-94A-6 as reported in IE Report 339/79-13. This print was compared to FSAR figure 5.5.4-1 dated November 3,1973.
(1) Ten vents or drains are incorrectly shown in the FSAR (339/
79-22-05).
(2) Three other piping connections are not correctly depicted in the FSAR (339/79-22-06). As in b. above, details of these problems were left with the licensee and will be followed up on future inspections.
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