IR 05000327/1979034
| ML19211C682 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/25/1979 |
| From: | Conlon T, Miller W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19211C675 | List: |
| References | |
| 50-327-79-34, 50-328-79-19, NUDOCS 8001140194 | |
| Download: ML19211C682 (5) | |
Text
."
'o
UNITED STATES l'
NUCLEAR REGULATORY COMMISSION n
E REGION 11
o,
~[
101 MARIETTA ST., N.W SulTE 3100 b
ATLANTA, GEORGIA 30303
%
o
'
Report Nos. 50-327/79-34 and 50-328/79-19 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, Tennessee 37401 Facility Name:
Sequoyah Docket Nos. 50-327 and 50-328 License Nos. CPPR-72 an' CPPR-7 Inspector:
/
<
C'
/r i/77
.
W. H. Miller, Jr. Uf Date Signed f
Approved by:
' k-T v t 'v y 4,
,4 /r'/ /
<.
/
T. liK ConIon, Section Chief, RCES Branch Date signed SUMMARY Inspection on October 2-5, 1979 Areas Inspeci.ed This routine unannounced inspection involved 25 inspector-hours onsite in the area of fire protection.
Results Of the area inspected, no items of noncompliance were identified; however, three deviations were found [ Deviations-Substandard automatic sprinkler system instal-lations-Paragraph 5.b(2); Inadequate QA documentation of inspections and tests conducted on fira protection system ins;a11ations-Paragraph 5.b(3); and, Failure to provide housing for reactor coolant pumps-Paragraph 5.b(4)].
1742 271 8001140I94
.
.
DETAILS 1.
Persons Contacted Licensee Employees
- G. G. Stack, Construction Project Manager
- J. M. Munns, Supervisor Construction QA
- H. Fisher, Mechanical Engineering R. Miles, Coordination Supervisor
- R. W. Farrell, Supervisor QCRV
- J. L. Smith, ACE / Construction
- C. Wagner, Coordination J. Thompson, Coordination
- M. A. McBurnett, Nuclear Engineer, Reg. Staff
- L. G. Hebert, OEDC QA Staff
- H. E. Crisler, ENDES, Sr. Mechanical Engineer
- R. T. Wimbrow, ENDES Mechanical Engineer
- G. B. Lubinski, EEU/ Supervisor
- C. W. Rice, EEU
- S.
V. Emert, Coordination
- R. Jarvis, Mechanical Engineer E. Conlon, Start-up and Test T. Le, Start-up and Test NRC Resident Inspector W. Cottle
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on October 5, 1979 with those persons indicated in Paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items
.
Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviations. New unresolved items identified during this inspection are discussed in paragraph 5.b.1.
1742 272
.
-2-
.
5.
Permanent Plant Fire Protection Systems A review of the installation documents, available inspection and test a.
documents and a visual inspecticn was made of the following permanent plant fire protection systems:
(1) Fire pumps - Units 1 and 2 (2) Reactor coolant pump fire suppression system - Unit 1, (Pumps 1 and 3)
(3) Reactor Coolant Pump oil collection system - Unit 1, Pumps 1 and 3 (4) Reactor building sprinkler systems - Unit 1 (5) Reactor building standpipe system - Unit 1 (6) Cable spreading room automatic sprinkler system - Units 1 and 2 (7) Battery room automatic sprinkler system - Units 1 and 2 (8) Control building standpipe system - Units 1 and 2 b.
Findings (1) Section E.2.(c) of the licensee's Fire Protection Program Reevaluation (FPPR) dated January 20, 1977, and item 8 of the March 9, 1979 Revisions to the FPPR, state that the fire pumps at the plant are not designed nor installed in accordance with the National Fire Protection Association Standard No. 20 (NFPA-20),
Centrifugal Fire Pumps.
A review of the installation documents and pump installations confirms these statements. However, this review also revealed several itees previously not addressed which appear to reduce the reliability of the fire pump installation.
These items are as follows:
(a) The power supply circuits and associated power supply pro-tective devices are not designed to meet the locked rotor current rating of the fire pumps as required by Sections 6-3.4-2 and 7-4.2 of NFPA-20.
.
(b) The pump starting circuits from the automatic water fire suppression systems are not electrically supervised as required by Section 7-5.2.5 of NFPA-20.
(c) The pumps are not arranged for automatic operation upon decrease of water pressure in the system and will not automatically start upon use of exterior fire hydrants by the fire brigade as required by Section 7-5.2.1 of NFPA-20.
I7142 273
.
-3-
,
(d) The fire pump controllers / motor starters are located within the control building and the pumps are located at the intake pumping structure resulting in long runs of power cables which are not supervised nor energized. Section 7-2.1 of NFPA-20 state that the fire pump controllers shall be as close as practical and within sight of the motor they control.
These items are identified as Unresolved Item (50-327/79-34-01 and 50-328/79-19-01), Substandard Fire Pump Installation, pending further review by the NRC.
(2) Sections E.3.(c), F.1.E, F.1.F, F.1.G and F.2.F of the FPPR state that the water fire suppression systems will be designed and installed to meet the provisions of hTPA-13, Automatic Sprinkler Systems, and NFPA-15, Water Spray Fixed Systems.
The sprinkler systems inspected contained the following discrepancies:
(a) The pre-action sprinkler system piping is not supervised as required by Section 5-3.5.2 of NFPA-13.
(b) The systems are not provided with adequately sized " test pipes" (main drains) arranged to permit full flow tests to assure that the water supply piping and connections are in order as required by Section 2-9 of NFPA-13.
(c) The activation circuits from the fire detection systems to the deluge / pre-action valves are not electrically supervised as required by Section 5-3.5.2 of NFPA-3 and Section 8-5 of NFPA-15.
(d) The control valves to the alarm and water flow devices are not of the type which can be sealed or locked in correct position as required by Section 3-17.4.5 of NFPA-13.
These items constitute a failure to meet a commitment to the NRC and are identified as Deviation Item (50-327/79-34-2 and 50-328/79-19-2), Substandard Automatic Sprinkler System Installations.
(3) Sections C.4, C.5, and C.7 of the initial FPPR and the revisions of March 9, 1979, state that the installation of the fire protec-
.
tion systems will be accomplished by construction documents with installation verified by independent inspections and test conducted in accordance with written procedures and with adequate records to be maintained to document that the systems conform to lhe prescribed criteria.
Presently, documentation is not provided on the hydrostatic pressure tests and flushing tests conducted on the fire protection systems. Also, permanent plant records are not provided on the functional tests conducted on the fire detec-tion systems. These inspections and test in conjunction with adequate documentation are required by the applicable NFPA Code /
1742 274
.'
-4-
.
Standard and are also specified in the construction documents.
The lack of adequate documentation for tests conducted on the fire protection systems is a failure to meet a commitment to the NRC and is identified as Deviation Item (50-327/79-34-3 and 50-328/79-19-3), Inadequate QA Documentation of Inspections and Tests Conducted on Fire Protection System Installations.
(4) Sections F.1.B and F.1.F of the FPPR state that a noncombustile housing will be provided for each reactor coolant pump. The housing was to enclosure the pump to contain a 3 dimensional combustile liquid discharge and to act as a heat collector to reduce the response time of the fire suppression system. However, in lieu of a ho; sing, a metal oil catch basin has been provided beneath each pump and a metal canopy has been provided above each pump. The fusible type fire suppression nozzles are not located beneath this canopy. This item is a failure to meet a commitment to the NRC and is identified as Deviation Item (50-327/79-34-4 and 50-328/79-19'4), Failure to Provide Housing for Reactor Coolant Pumps.
Except as noted above, within the area inspected, no additional items of noncompliance or deviations were identified.
6.
QA Records Storage The QA/QC inspection records and other construction record data are stored in two storage facilities slightly detached from one of the temporary construction administration buildings. The record storage facilities are of fire resistive construction with the door opening into each facility protected by a 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (Class A) rated, self-closing fire door. The storage facilities comply with the intent of ANSI Standard N45.2.9, " Requirements for Collection, Storage and Maintenance of QA Records for Nuclear Power Plants" and Regulatory Guide 1.88, " Collection Storage and Maintenance of Nuclear Power Plant QA Records" except the storage facilities are not provided with an automatic fire suppression system.
Presently, the licensee does not have a commitment with the NRC to provide a QA records sterage facility meeting the criteria of ANSI-N45.2.9 or RG-1.88 since this criteria did not exist at the time the construction permit for the plant was issued.
It was suggested that the liceuree re-evaluate the QA records storage facility to assure that adequate fire protection features are provided or duplicate records maintained as required
.~
by current criteria.
1742 275