ML20205K180
| ML20205K180 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 02/25/1986 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20205K184 | List: |
| References | |
| NUDOCS 8602270181 | |
| Download: ML20205K180 (4) | |
Text
Pubhc Service Electric and Gas Cornpany Ccrbin A. McNeill, Jr.
Pubhc Service Electric and Gas Company P.O Box 236, Hancocks Bridge. NJ 08038 609 339-4800 Vice President -
Nuclear February 25, 1986 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention:
Ms. Elinor Adensam, Director Project Directorate 3 1
Division of BWR Licensing
Dear Ms. Adensam:
ENVIRONMENTAL QUALIFICATION HOPE CREEK GENERATING STATION DOCKET NO. 50-354 This letter provides follow-up information and responses to items listed in our equipment qualification program letter dated January 7, 1986 (C.A. McNeill, PSE&G to E.
Adensam, NRC), and responses to NRC requests for information j
discussed with Mr.
H. Garg on January 21, 1986.
j 1.
Field inspection 66d~ verification - GE has replaced the two (2) Rosemount 1152 transmitters identified in our January 7, 1986 letter with qualified 1151 trans-mitters and has performed a physical review of all Rosemount transmitters supplied by them and confirms that the equipment matches their design documents.
2.
Confirm that maximum normal service temperature in lieu of average temperature has been factored into EQ program - EQ documents which have been revised to reflect that maximum normal service temperature instead of average temperature was used as the basis for quali-fication, have been included in the maintenance program in accordance with the existing procedure for equipment qualification maintenance and surveillance requirements.
3.
Confirm that Class lE qualification is complete - All the equipment is now qualified to the harsh-(10CFR50.49)
Class lE environmental qualification including the General Atomics radiation monitoring system components.
8602270181 860225 PDR ADOCM 05000354 1
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Director of Nuclear-2 2-25-86.
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Reactor Regulation O
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Environmental Qualification Summary Report - Enclosed-for NRC review are two (2) copies of Revision 4 of j
the Environmental Qualification Summary Report for Hope Creek Generating Station.
The report incorporates comments provided by H. Garg in December-1985, as well i
as all remaining Equipment Evaluation Summary Sheets
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(EESS) and final updated HCGS FSAR tables.
These updated tables will be-included in a future amendment to'the-HCGS FSAR.
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5.
Maintenance and surveillance program - All Hope' Creek j
maintenance and surveillance procedures include equipment environmental qualification requirements and training i
of technicians in the use of these procedures has been j
completed.
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During the meeting held at the NRC Bethesda offices on January 21, 1986, H.
Garg requested confirmation that Information-l Notices 83-72 and 86-02 regarding internal wiring and magnesium rotors in Limitorque actuators, respectively, have been 5
evaluated and the subject equipment found acceptable.
Information Notice 83-72 was reviewed previously by both l
Bechtel and PSE&G.
Our original < documentation for HCGS l
Limitorque actuators states that prequalified wire / insulation i
was used.
To substantiate this we reviewed our qualification i
files for Limitorque actuators.
Limitorque BWR Qualification Report - Containment Chamber i
Service - #600376A, Addendum A addresses ' Wire Qualification' in Section 3.1.lC.
This report refers to two qualification
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documents for wiring:
'l 1.
File Report #F.C 4033-l&2 (RAYCHEM) for Flamatrol wire having radiation-cross-linked polyolefin insulation, and i
4 2.
Rockbestos Report " Qualification of Firewall III, having i
irradiation cross-linked polyolefin insulated cable.
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Qualification Report #QR-1806.
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Both reports, which are contained in our EQ files, have i
been reviewed and are acceptable for HCGS safety related application in a harsh environment.
l In addition to internal wiring supplied by Limitorque, wiring modifications made on site which add / replace internal j
wiring must also be controlled and qualified in accordance i
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Director of Nuclear 3
2-25-86 Reactor Regulation with our program per 10CFR50.49.
" Potential Deficiencies in Environmental Qualification of Limitorque Motor Valve Operator Wiring" issued on January 14, 1986 addresses wiring added by others.
Installationbof additional wiring in safety-related equipment at HCGS is governed / controlled in accordance with the following:
a)
EE580 for cable terminations b)
Specific work plan / procedure - SWP/P-E-18 c)
Wire and cable notes and details - E-1408 d)
Electrical cable description - E-1000-0 Section 3.6.2 of E-1408 states; " Wiring Modifications to Class lE valves in the Reactor Building and the drywell (including the torus) shall be made with cable codes S13 and S14, or wiring supplied by the valve supplier".
S13 and S14 are supplied under PO E-170A(Q) which has been reviewed and approved in accordance with the HCGS Harsh Environmental Qualification program (EESS No. 11).
Therefore, original and added wiring for safety-related Limitorque actuators have been adequately addressed for HCGS.
Information Notice 86-02 " Failure of Valve Operator Motor During Environmental Qualification Testing", specifically Limitorque valve operators with magnesium rotors installed in containment, was evaluated based on earlier receipt of General Electric SIL No. 425.
Five (5) valves were identified within the drywe.1 which have magnesium rotors.
Four (4) of the valves are maintenance block valves at the suction and discharge of the reactor recirculation pumps.
The fifth is the RHR shutdown cooling suction inboard containment isolation valve (lBCHV-F009).
Each valve has been evaluated with respect to their function following a LOCA.
The four (4) reactor recirculation pump block valves are used for isolation of the pumps under maintenance activities and are not required for long-term core and containment cooling.
The RHR shutdown cooling suction valve is connected to Class lE power.
The proper valve alignment for this valve for long-term core cooling will be established in accordance with procedure OP-EO.ZZ-099Q, Post Scram Restoration, which is expected to be prior to seven (7) days into a post-LOCA period.
Should the valve operator fail at any time before proper alignment is made, alternate shutdown cooling is initiated in accordance with procedure OP-AB.ZZ-142Q or OP-EO.ZZ-205Q which do not require any use of this valve.
Director of Nuclear 4
2-25-86 Reactor Regulation Thus, the ability to provide adequate long-term cooling for the reactor core would not be jeopardized if this valve operator were to fail seven (7) days after a LOCA.
In addition, the power supply for the valve operator is protected with double breakers, with contactors open with the valve in the open or closed position.
Therefore, the failure identified in Information Notice 86-02 has been evaluated and found not to be a safety concern for HCGS.
This documentation completes our response to all open items related to the Hope Creek Environmental Qualification Program.
Sincerely, C A B7 'JLd i[
f Enclosure C
D.H.
Wagner (2 copies of enclosure)
USNRC Licensing Project Manager R.W. Borchardt (w/o enclosure)
USNRC Senior Resident Inspector H.
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