IR 05000327/1980017
| ML19327A131 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/02/1980 |
| From: | Conlon T, Miller W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19327A101 | List: |
| References | |
| 50-327-80-17, 50-328-80-10, NUDOCS 8008010184 | |
| Download: ML19327A131 (5) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
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101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 JUN - 51980 Report Nos. 50-327/80-17 and 50-328/80-10 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Facility Name: Sequoyah Docket Nos. 50-327 and 50-328 License Nos. DPR-77 and CPPR-73 Inspection at S quoyah site near tanooga, Tennessee Inspector:
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W. H. Miller, Jr.
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l 3 D6te / Signed Approved
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b 4 -J2- [o T. E. C6alon, Section Chief, RCES Branch Date Signed
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.I SUMMARY Inspection on May 13-15, 1980 Areas Inspected This special, announced inspection involved 23 inspector-hours on site in the areas of fire protection / prevention.
Results Of the areas inspected, no items of noncompliance were identified; one deviation
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(deviation - inadequate fire barriers for conduits containing steam generator instrumentation circuits - Paragraph 5.a) was identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- G. G. Stack, Construction Project Manager
- T. B. Northern, Construction Engineer
- J. M. Munns, QA Unit Supervisor
- J. L. Smith, ACE - Construction
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- J. Bynum, Nuclear Power H. Crisler, ENDES - MEB
- R. E. Thompson, Nuclear Power - Supervisor Fire Protection Engineer
- M. A. McBurnett', Power - Regulatory Staff
- D. Wall, OEDC - Licensing B. Nicholson, ENDES - SWP l
- E. C. Pendergrass, Construction - QCRU
- E. A. Craigge, Safety / Fire Protection
- R. Miles, Coordination Supervisor
- H. Fisher, Mechanical Engineering C. Cherry, Startup Coordination R. C. McKay, Civil Engineer
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R. Ector, Outage Department 1 ~~~-
M. L. Cowan, Outage Department
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R. Jarvis, Mechanical Engineer NRC Resident Inspector
- W. T. Cottle
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on May 15, 1980 with those persons indicated in Paragraph I above.
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Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (327/79-34-01 and 328/79-19-01, Substandard fire a.
pumps installation. By telephone conversation of May 16, 1980, G. A.
Harrison of NRC/NRR advised W. H. Miller, Jr., of NRC Region II that the existing fire pump installation at Sequoyah was acceptable to NRR and that es further modifications or changes were required on this
system. Therefore, this item is closed.
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(Closed) Deviation (327/79-34-03 and 328/79-19-03), Inadequate QA docu-mentation of inspection and tests on fire protection system installa-tions. A QA program meeting all of the requirements of NRC Branch Technical Position 9-5.1, Fire Protection Program, Appendix A was not provider for the installation and construction of fire protection
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systems and features at the plant. The fire protection systems installed since 1977 were inspected by a responsible engineer and inspector to assure the installations were in conformance with the construction drawings.
These inspections were documented. The licensee advised that systems installed prior to 1977 were inspected to assure conform-ance but inspections were not documented.
Ir. addition, construction documentation was apparently not provided for any of the flushing and i
hydrostatic pressure tests conducted on the systems. A review of TVA Pre-operational test 25C indicates that the piping systms were flushed at the designed flow rate. These tests are considered adequate for meeting the required flushing documentation. The licensee has reviewed log entries and other data to assure that the entire fire protection water piping system was properly hydrostatially tested. TVA's letter from L. M. Mills to James P. O'Reilly Director, RII dated May 22, 1980 confirms that these tests were performed.
The functional tests on all of the fire detectors were witnessed by a responsible engineer and these tests were documented. A random sample of the detectors were tested during the pre-operational tests. Surveil-lance Inspection SI-234 completed in November 1979 verified that all of the detectors had been properly tested. Based on the above, this item is closed.
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(Open) Deviation (327/80-10-01), Substandard fire protection admini-
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strative control procedures.
The licensee's prccedures have been revised to require quarterly fire brigade classroom training for the
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brigade and to require at least one fire brigade drill per year per shift to be conducted on the back shift.
The licensee has taken exception to the deviation concerning the lack of fire fighting procedures for all safety-related areas and the use of fire retardant painted wood in lieu of pressure fire retardant type treated wood in safety-related areas of the plant. This item remains open pending further evaluation by the NRC.
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(Open) Deviation (327/80-10-02), Substandard supervision of fire protection control valves. The licensee has revised the surveillance procedure for the interior control valves to the fire suppression
systems to require these valves to be sealed in the correct position and inspected weekly for proper alignment.
The exterior control valves and the fire pump control valves will be locked in the correct
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position and inspected monthly for properly alignment. The licensee's proposal is consistent with the provision of National Fire Protection Association Standard 26 (NFPA-26), Supervision of Valves, but does not comply with previous commitment to the NRC. This item remains open
pending further evaluation.
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(Open) Unresolved Item (327/80-10-03), two inch drain test for sprinkler
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system. This item is being evaluated by the licensee, i
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(Closed) Unresolved Item (327/80-10-04), Tests of Unsupervised fire protection system circuits.
The licensee's surveillance inspection procedure (SI-234) has been revised to require a semi-annual test of all unsupervised alarm system circuits. This item is closed.
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(0 pen) Unresolved Item (327/80-10-05), Equipment for exterior fire equip-ment houses. The licensee is to revise the equipment requirements for the exterior fire equipment storage houses. This item will remain open pending NRC's (NRR) review of the licensee'r proposed equipment list.
h.
(Closed) Unresolved Item (327/80-10-06), Tests of supervisory features of fire alarm control panel. These tests have been included in the surveillance inspection procedure (SI-234) for the fire alarm system.
Therefore, this item is closed.
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(0 pen) Unresolved Item (227/80-10-07), Supervision of containment isolation fire protection valves. No action has been taken on this item. This item remains open.
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(Closed) Unresolved Item (327/80-10-08 and 328/80-06-08), Unprotected penetratioa in fire wall of fuel oil transfer room at diesel generator building.
Necessary modifications have been made to correct this discrepancy. This item is closed.
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Unresolved Items
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Unresolved items were not identified during this inspection.
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Fire Protection Modifications a.
Conduit Fire Barriers l
TUA's response to NRC question No. 1 on the Fire Protection Program Eeevaluation (FPPR) states that the redundant circuits for the steam generator pressure instrumentation were inadequately separated. Table 1.3 of the FPPR states that the circuits for loops 2 and 3 steam generator pressurizer level and pressure instrumentation for Unit 1
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were to be wrapped with a 1-inch "Kaowool" insulation from the contain-ment penetration at elevation 734 to the Q-line wall penetration at elevation 714. This insulation was to provide a 1/2 hour fire rated barrier between redundant circuits and installation was to be completed prior to October 5,1979. A visual inspection of these conduits on May 15,1980 indicated the following:
(1) Approximately 4 feet of all seven conduit adjacent to column line AS/X at elevation 714 were not insulated.
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(2) Several short sections of conduit adjacent to column line A4/W were not insulated.
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(3) Three conduit fittings adjacent to column line A4/U at elevation 714 did not contain cover plates.
The conduit fittings and connecting conduit in this area were not insulated.
This item was identified as Deviation Item (327/80-17-01)'; Inadequate fire barriers for conduits containing redundant steam generator instru-
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mentation circuits.
b.
Other Modifications i
The licensee advised that several other modifications would probably not be completed prior to the committed completion dates and a revised completion schedule was being forwarded to NRC/NRR for review. These modifications will be evaluated during a subsequent NRC inspection.
Except as noted above, no additional items of noncompliance or deviations were noted in the areas examined.
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