ML20150A668
| ML20150A668 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 09/22/1978 |
| From: | Crane P PACIFIC GAS & ELECTRIC CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7810030210 | |
| Download: ML20150A668 (5) | |
Text
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P.A.C I F' I C GAS AND ELECTRIC C C M PANY-h T7DNb l
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- SAN FRANCISCO, CALIFORNI A 9410fs (415) 78).4 h 1 s
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e H a nL c e w. t nia s e L L Mr. John F. Stolz, Chief Light Water Reactors Branch No. 1 d
Division.of Project Management
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U. S. Nuclear Regulatory Commission y
Washington, D. C. 20555 g'$q l
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Docket No. 50-323-OL g
Diablo Canyon Units 1 & 2 g
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Dear Mr.-Stolz:
Enclosed are 40 copies of a revision of the table entitled " Environmental Qualification of Class IE Equipment with Potential for Exposure to a Severe Environment.
Earlier versions of this table were enclosed with our letters.of May 3, 1978 and July 28, 1978.
This revision addresses additional informal Staff questions on environmental qualification of equipment, and relates to open Item (3), Page 7-7, Section 7.8 of SER Supplement 7.
Five copies of this submittal have been sent directly to Mr. Dennis Allison.
Kindly acknowledge receipt of the above material on the enclosed copy of this letter and roturn it to me in the enclosed addressed envelope.
Very truly yours, Philip A. Crane, Jr.
Enclosures l,
CC w/ enc.:
Mr. 9ennis Allison Service List 18/0030
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i TABLE 3.11-1A ENVIRONMENTAL QUALIFICATION e Sheet 1 of 3
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' CLASS IE EQUIPMENT' WITH POTENTIAL FOR EXPLOSURE TO A SEVERE ENVIRONMENT j
Class IE Equipment Inside Containment - Subject to LOCA
^
l Equipment' Manufacturer Typ_e,(Model No.)
Qualification Citation e
1.
Pressure and Differential 4
l-Transmitters a.
Pressurizer Pressure
- Rosemount 1152 Rosemount' Report #117415 b.
Pressurizer Level ITT Barton 764 FSAR Paragraph 3.11.3-7 l
c.
Containment Sump Level ITT Barton 764 FSAR Paragraph 3.11.3-7 d.
Reactor Coolant System ITT Barton 763 FSAR Paragraph 3.11.3-7 i
Wide Range Pressure e.
Narrow Range Steam ITT Barton 764 FSAR Paragraph 3.11.3-7 i
Generator Level f.
Steam Flow
- Rosemount 1152 Rosemount Report #117415 i
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i g-Sensor for Containment Pressure Barton 351 PGandE Letter to NRC 9-21-78 2
l 2.
Resistance Temperature
. Detector a.
Reactor Coolant System Sostman 11834B-1 PGandE Letter to NRC Temperature 9-21-78
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3.
Valve Motor Operators Limitorque SMB-0, 00, 000 FSAR Paragraph 3.11.3-7 4.
Containment Fan Cooler Westinghouse 300/100 h.p.
FSAR Paragraph 3.11.3 WCAP 7829 - Fan Cooler Motor Test PG&E letters to NRC 2-10-78 and 1/19/78
- Required for Initiation Only
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(September 1978)
Amendment 69 4
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Sheet 2 of 3
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Equipment Manufacturer Type (Mod'e1 Jo.).
Qualification Citation 5.
Electrical Penetrations General Electric NS02/03/04 Record Numbers 663081-18, 19 & 20 FSAR Paragraph 3.11.3-6 l
6.
Electrical Cables
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l Continental Silicon / Silicon Continental Test Report CC-21935 y
(3/71)
Boston Silicon /Hypalon Record Number 663359-20 Raychem Stilan Raychem memo on LOCA Testing at Franklin Institute Labs (2/10/75)-
Okonite Tefzel Record Number 663359-69 i
Boston Silicon Glass Briad/
.PG&E Engineering Research Test Kapton/Hypalon Report LSS-1586 (3/5/71) j,-
7.
Electrical Teminations Raychem Sealed Splice Franklin Institute Report
- F-C 4033-3 (1/75)'
i FSAR Paragraph 3.11,3-5 8.
Stem Mounted Limit Switches Namco EA180 Acme Cleveland Report (3/3/78) 9.
Containment Isolation ASCO 8300 FSAR Paragraph 3.11.3-3 Solenoid Valves 8302 8316*
8321*
j Class IE Equipment Outside Containment - Subject to High Energy Line Break 1.
Electrical Cables Raychem Flamtrol Raychem Test Report EM 1030 (9/24/74)
Okonite EPR/0kolan,(Hypalon)
Okonite Test Report (10/14/74) 2.
Feedwater Flow Sensors Fischer and Porter 10B2496PBBA 7410-L i-3.
Main Steam Line Pressure Fischer and Porter 50EP1041BCX WCAP 7410-L 4.
Aux. Feedwater Isolation Valve Limitorque SMC-04 Motor Operators OSpecial valves with all plastic parts replaced with stainless steel or brass parts to withstand higher temperatures.
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'(September 1978)
Amendment 69 s
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Sheet 3 of 3
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Equipment Manufacturer Type (Model No.)
Qualification Citation Class IE Equipment not required to Function in a Severe Environment 4
1.
Reactor Coolant Flow Fischer and Porter 10B2496PBBA WCAP 7410-L (Radiation only) 2.
Containment Pressure ITT Barton 332 N/A
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4 (September 1978)
Amendment 69 3
7
. NOTES FOR-TABLE 3.ll-1A (ProvidedinResponsetoInformalStaffRequest During July 31 - August 11, 1978 Meetings)
Justification for the Exclusion of the Auxiliary Feedwater Level Control Valves From the Severe Environment Exposure List Auxiliary feedwater is supplied to the steam generators by one turbine driven and two motor driven auxiliary feedwater pumps.
The turbine driven pump has sufficient capacity to supply emergency feedwater to four steam generators.
l Each motor driven pump has sufficient capacity to supply emergency feedwater to two steam generators.
The turbine driven pump isolation valves are manually positioned motor operated valves (MOV).
The motor driven pump's steam generator level control valves are automatic, electro-hydraulically operated valves (E-H) with manual override.
Two turbine driven pump level. control valves and the two E-H level control valves for one motor driven pump are located in plant area F pipeway near the main steam and main feedwater containment penetrations for steam generators 1 and 2.
The other two turbine driven pump level control valves and the two E-H level control valves for the second motor driven pump are located in plant area GE, elevation 115'-0", near the main steam and main feedwater containment penetrations for steam generators 3 and 4.
Plant areas F and GE are diametrically opposite on the containment structure.
Plant area F it outdoors and area GE is inside the Auxiliary Building.
If a main steam line break were to occur in either plant area, two M0V isolation valves.and two E-H control valves would be subjected to an environmental temperature that rises to a inaximum of 212*F for 300 seconds and stabilizes at 200*F.
The MOV's are environmentally qualified and are shown on the sev: re environment list.
The E-H's have not been tested for
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this type of environment.
y 1
If this condition caused a failure of the E-H actuators, the motor driven pump to these valves could be shut off.
Since they feed the steam generator which would be feeding the break, this is not only acceptable, it is desirable.
The M0V to the affected steam generator could be closed, and the turbine driven pump could supply the 3 unaffected steam generators.
As a backup, the motor driven pump to the unaffected E-H valves could supply the two unaffected steam generators on the other side.
l Therefore, the auxiliary feedwater level control valves are not required to be qualified for a severe environment.
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(September'1978)
Amendment 69
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