ML19291C087
| ML19291C087 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 11/08/1979 |
| From: | Parker W DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19291C080 | List: |
| References | |
| NUDOCS 8001180405 | |
| Download: ML19291C087 (4) | |
Text
I DUKE POWER COMPANY Powra Britorwo 422 SorTu Cutacu Srnrer, CruutorTE, N. C. 28242
- r-
'e WIL LI AM O. PA R M E R, J R.
v,ec p.c.>ocar November 8, 1979 Tet r a-o~ c: ^= ci 7 4 Sttana P.oosevion 373-4063 Mr. J. P. O'Reilly, Director U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, GA 30303 Re: RII:WHM 50-369/79-34 50-370/79-20
Dear Mr. O'Reilly:
Attached is Duke Power Company's response to IE Inspection Report Nos. 50-369/79-34 and 50-370/79-20 which was transmitted by your letter of October 19, 1979.
Duke Power Company does not consider any information contained in this inspection report to be proprietary.
Very'truly yours, f
7
&_ a cu a William O. Parker, Jr. []
THH /sch Attachment PRoGeg#rp
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MCGUIRE NUCLEAR STATION Response to IE Report Nos. 50-369/79-34 and 50-370/79-20 NOTICE OF DEVIATION Duke Power Company License Nos. CPPR-83 McGuire
& CPPR-84 Based on the results of the NRC inspection conducted on September 11-14, 1979, certain of your activities appeat to deviate from your commitments to the Commission and have safety significance as indicated below:
A.
Section 17.1.17.4 of the FSAR states that the QA records storage facility will meet the provisions of ANSI Standard N45.2.9, " Requirements for Collec-tion Storage and Maintenance of QA Records for Nuclear Power Plants".
Section 5.6 of ANSI N45.2.9 requires QA records storage facilities to be provided with a fire protection system.
Duke's OA Procedure QA-301 requires construction site QA storage facilities to be provided with either a dry chemical or gas fire suppression system.
Contrary to the above, the construction site QA records storage facility is not provided with an automatic fire suppression system.
B.
Sections E.3. (c) and E.3. (d) of the licensee's Fire Protection Review (FPR),
January 1978 revisions, states that fire protection piping systems will be installed to meet the applicable National Fire Protection Association (NFPA) standards.
Section 8-8.2 of NFPA-24, "Outside Protection", Section 1-11.2.2 of NFPA-13, " Sprinkler Systems" and, Section 7-1.2.1 of NFPA-14, " Standpipe and Hose Systems indicate the minimum flow required to properly flush the fire protection water supply piping systems."
Contrary to the above, Duke's Construction Procedure CP-419 provided a description for flushing the fire protection piping systems but fails to indicate the rate of flow required to flush the systems. Therefore, it appears that portions of the piping systems may not have been adequately flushed.
C.
Section F.7 of the licensee's FPR states that the area beneath the cable trays in the west portion of Unit 1 Battery Room 701 will be provided with an automatic sprinkler system to protect the cable concentrations from an exposure fire.
Section E.3(c) of the FPR states that the automatic sprinkler systems installed at the plant will meet the provisions of NFPA-13
" Sprinkler Systems".
Contrary to the above, the sprinkler system for the west portion of Unit 1 Battery Room 701 does not meet the provisions of NFPA-13 due to the following:
1.
Upright type sprinkler heads are installed in the pendent position which is not permitted by Section 3-16.2.2 of NPFA-13, 2.
Sprinkler heads are installed beneath the lowest cable tray elevation and are not provided with heat shields as required by Section A-3-16.8 of NFPA-13.
These shields are shown on the construction drawings.
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3.
Sprinkler protection is not provided between column lines 53AA/54AA and 53BB/54BB.
The distance between the end sprinkler head and the wall at column line 53AA/54AA is approximately 18 feet and this end head is also obstructed by the structural supports for the cable trays. Sections 4-2.1.4 of NFPA-13 requires that the maximum distance between the walls and end sprinkler heads not exceed 7.5 feet and Section 4-2.4.6 of NFPA-13 requires additional sprinkler heads for areas where protection is obstructed by structural supports.
4.
Provisions are not provided to properly test the water flow alarm indicator. Sections 3-9, 3-17.4 and 3-17.6 of NFPA-13 require that waterflow alarm detection devices be arranged to permit testing by actual waterflow.
The test connection is required to be arranged as indicated by Figure A-3-9.1.2 of NFPA-13.
5.
Operation of the waterflow alarm device will not activate the deluge valve in the water supply piping system to the auxiliary building as required by Sections 5-1.1 and 5-3.1 of NFPA-13.
These same discrepancies may also be applicable to other systems installed at plant.
D.
Sections E.3.(c) and E.3.(d) of the FPR state that the fire protection piping systems will conform to the applicable NFPA standards (NFPA-13,
" Sprinkler Systems"; NFPA-14, " Standpipe and Hose Systems"; and, NFPA-15,
" Water Spray Fixed Systems").
Contrary to the above, the water supply piping to the fire protection systems within the auxiliary building does not meet the applicable NFPA standards due to the following.
1.
Normally closed deluge valves which control the water supply to the auxiliary building are manually activated from manual stations within the auxiliary building and control room by electrical circuits which are not electrically supervised as required by Sections 1-6.1 and 5-3.6 of NFPA-13 and 8-5.2 of NFPA-25.
2.
The sprinkler systems waterflow alarm devices are not arranged to activate the deluge valves controlling the water supply to the fire protection piping systems as required by Sections 5-1.1 and 5-3.1 of NFPA-13.
3.
The arrangement of the 1-inch by-pass and proposed associated alarm devices will not provide a reliable means of supervising the piping systems as required by Sections 3-14.2.3 and 5-3.5.2 of NFPA-13.
Response
A.
An automatic fire suppression system for the QA records storage facility is not required by Section 5.6 of ANSI N45.2.9.
Duke Power Company provides a fire protection extingeishing system for the QA records storage facility through the use of portable dry chemical fire extinguishers mounted both inside the room and immediately outside the door to the room.
In addition smoking inside the room is prohibited.
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In order to provide further assurance of adequate fire protection, a smoke detector is currently being installed in the QA records storage facility.
This smoke detector will alarm in the No. 1 Construction Guard Gate which is manned 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day.
The smoke detector will be operable by January 1, 1980.
B.
Duke Power Company has conducted a test of portions of the fire protection piping systems to measure the flowrate during pipe flushing. This test revealed that the measured flowrate was well above the demand flowrate for the systems tested.
Flushing these piping systems at or above the demand flowrate and with a sufficient volume of water to achieve a clear discharge satisfies the requirements of Section 8-8.2 of NFPA-24, Section 1-11.2.2 of NFPA-13, and Section 7-1.2.1 of NFPA-14.
The McGuire Nuclear Station Technical Specifications require flushing of the fire protection piping at periodic intervals using a flowrate in excess of the demand rate of the system.
This flowrate will be verified to be in excess of the system demand rate.
The first of these periodic piping flushes will be conducted within six months of fuel loading.
C.
1.
The affected upright type sprinkler heads will be replaced with pendant type sprinkler heads by February 1, 1980.
2.
Heat shields will be installed on those sprinkler heads beneath the lowest cable tray elevation by February 1, 1980.
3.
Automatic sprinkler protection has not been provided between column lines 53AA/54AA and 53BB/54BB since no cabic tray stacks are located in this area. All sprinkler heads which are obstructed by the structural supports for the cabic trays will be relocated by February 1, 1980.
4.
A test connection for the waterflow alarm indicator will be added to permit testing by actual waterflow. This modification will be complete by February 1, 1980.
5.
See response to item D below.
D.
The two deluge valves serving the Auxiliary and Reactor Buildings are normally closed to preclude the possibility of incapacitating safe shutdown systems or components due to flooding resulting from failure or inadvertant operation of the fire suppression system.
These deluge valves may be manually tripped open at the valve upon loss of electrical power.
In addition, the one inch bypass line around each deluge valve will maintain pressure on the headers and will provide sufficient water to supply any automatic sprinkler system or two hose stations without activating the deluge valves.
It is recognized that there are minor differences between the McGuire fire protection design and the NFPA standards.
These differences were recognized and evaluated by the Office of Nuclear Reactor Regulation during their review and acceptance of the McGuire fire protection system.
This review and acceptance is documented in Appendix D of the McGuire Nuclear Station Safety Evaluation Report Supplement No. 2.
The details of the McGuire fire protection system are described in Mr. W. O. Parker's November 2,1978 letter to Mr. H. R. Denton and in' the McGuire Fire Protection Review revised January 1979.
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