ML20203N705
| ML20203N705 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 10/09/1986 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20203N703 | List: |
| References | |
| NUDOCS 8610170211 | |
| Download: ML20203N705 (8) | |
Text
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i NUCLEAR REGULATORY COMMISSION
,. l WASHINGTON, D. C. 20555 GULF. STATES UTILITIES COMPANY DOCKET NO. 50-458 RIVER BEND STATION, UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 2 License No. NPF-47 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by Gulf States Utilities Company, dated September 17, 1986 and supplemented by letter dated September 19, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regu-lations set forth in 10 CFR Chapter 1; E.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-47 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 2 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. GSU shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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This license amendment became effective September 19, 1986.
FOR THE NUCLEAR REGULATORY COMMISSION
%I moned by Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 9,1986 y paa
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This license amendment l'acame 'effectivc September 19, 1986.
FOR THE NUCLEAR REGULATORY COMMISSION 1,
Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 9,1986
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4
1 ATTACHMENT TO LICENSE AMENDMENT NO. 2 FACILITY OPERATING LICENSE NO. NPF-47 DOCKET NO. 50-458 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and j
contain a vertical line indicating the area of change. Overleaf pages provided to maintain document completeness.*
REMOVE INSERT 3/4 6-35 3/4 6-35 3/4 6-36 3/4 6-36*
3/4 6-47 3/4 6-47 3/4 6-48 3/4 6-48*
i
TABLE 3.6.4-1 (Continued)
CONTAINMENT AND DRYWELL ISOLATION VALVES
.h MAXIMUM SECONDARY PENETRATION VALVE ISOLATION TIME CONTAINMENT gj)
SYSTEM VALVE NUMBER NUMBER GROUP (Seconds)
BYPASS PATH c.$
(Yes/No)
-4 H
a.
Automatic Isolation Valves 1.
Primary Containment (a). (Continued)
1E51*MOVF063(b) 1KJB*Z15 2
1E51*MOVF076(b)(m) 1KJB*Z15 2
13.4 No l
1E51*MOVF064 IKJB*Z15 2
9.9 No RCIC Pump Suc.-Supp. Pool IE51*MOVF031II) 1KJB*Z16 2
30.5 No RCIC Turbine Exh.-Supp. Pool IE51*MOVF077 IKJB*Z17 3
14.2 No m}
RCIC Turbine Exh. Vac. Bkrs.
1E51*MOVF078 1KJB*Z188,C 3
M5 No Cont./Drywell. Purge Sup.
1HVR*A0V165 1KJB*Z31 8
3 No a
Cont./Drywell Purge Sup.
1HVR*A0V123 IKJB*Z31 8
3 No Cont./Drywell Purge Outlet 1HVR*A0V128 1KJB*Z33 8
3 No m
Cont./Drywell Purge Outlet 1HVR*A0V166 IKJB*Z33 8
3 No Post-Accident Samp. Sup.
ISSR*S0V130 IKJ8*Z601B 10 3
No Post-Accident Samp. Sup.
ISSR*S0V131 1KJB*Z601B 10 3
No N
9 a
.E N
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TABLE 3.6.4-1 (Continued) m CONTAINMENT AND DRYWELL ISOLATION VALVES ll' MAXIMUM SECONDARY PENETRATION VALVE ISOLATION TIME CONTAINMENT II)
SYSTEM VALVE NUMBER NUMBER GROUP (Seconds)
BYPASS PATH (Yes/No)
-n da a.
Automatic Isolation Valves
- 2.
Drywell(k)
Cont./Drywell Purge Sup.
1HVR*A0V147 1DRB*Z32 1
3 No RPCCW Supply ICCP*MOV142 IDRB*Z50 1
30 No RPCCW Return 1CCP*MOV144 1DRB*Z51 1
30 No RPCCW Return ICCP*MOV143 1DRB*Z51 1
30 No Service Water Supply ISWP*MOV4A 1DRB*Z54 1
52.8 No
,,);
Service Water Supply ISWP*MOV4B IDRB*Z54 1
51.7 No Service Water Return ISWP*MOV5A 1DRB*Z55 1
50.6 No i'
Service Water Return ISWP*MOV5B 3DRB*Z55 1
53.9 No Recirc. Flow Control IRCS*MOV58A IDRB*Z152 1
11.0 No Recirc. Flow Control IRCS*MOV59A IDRB*Z153 1
10.6 No Recirc. Flow Control IRCS*MOV60A 1DRB*Z154 1
6.3 No Recirc. Flow Control IRCS*MOV61A 1DRB*Z155 1
8.6 No Recirc. Floy Control IRCS*H0V588 1DRB*Z156 1
10.6 No Recirc. Flow Control IRCS*MOV59B IDRB*Z157 1
10.8 No Recirc. Flow Control IRCS*MOV60B IDRB*Z158 1
6.38 No Recirc. Flow Control IRCS*MOV618 1DRB*Z159 1
8.9 No Cont./Drywell Purge Sup.
1HVR*A0V125 1DRB*Z32 1
3 Ho Cont./Drywell Purge Rtn.
1HVR*A0V126 IDRB'Z34 1
3 No Cont./Drywell Purge Rtn.
1HVR*A0V148 1DRB*Z34 1
3 No
TABLE 3.6.4-1 (Continued) i3 CONTATWENT AND DRYWELL ISOLATION VALVES m
NOTES
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(a) Subject to a Type C leak rate test at a test pressure of 7.6 psig except as otherwise noted.
zq (b) Also isolates the drywell.
)
(c) Testable check valve.
(d) Isolates on MS-PLCS air line high flow or MS-PLCS air line header to Main Steam Line low differential pressure.
(*) Receives a remote manual isolation signal.
(I) This line is sealed by the penetration valve leakage control system (PVLCS).
The combined leakage from
,g valves sealed by the PVLCS is not included in 0.60 La Type B and C test total.
(9) This valve sealed by the main steam positive leakage control system (MS-PLCS).
T Valves sealed by the O
MS-PLCS are tested in accordance with Surveillance Requirement 4.6.1.3.f to verify that leakage does not exceed the limit specified in Specification 3.6.1.3.c.
This leakage is not included in the 0.60 La -
Type B and C test total.
(h) Not subject to Type C leakage tests.
Valve (s) will be included in the Type A test.
(3) Valve is hydrostatically leak tested at a' test pressure of 8.36 psig (1.1 Pa).
The leakage from hydrostatically tested valves is not included in the 0.60 La Type B and C test total.
p (k) Not subject to a Type A, B, or C leak rate test.
II) Valve groups listed are designated in Table 3.3.2-1.
b") Valve IE51*MOVF076 is not required to be OPERABLE through October 4,1986.
O N
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CONTAINMENT SYSTEMS 3/4.6.5 SECONDARY CONTAINMENT SECONDARY CONTAINMENT INTEGRITY - OPERATING LIMITING CONDITION FOR OPERATION 3.6.5.1 SECONDARY CONTAINMENT INTEGRITY - OPERATING shall be maintained.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
Without SECONDARY CONTAINMENT INTEGRITY - OPERATING restore SECONDARY CONTAINMENT INTEGRITY - OPERATING within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the n' ext 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.5.1 SECONDARY CONTAINMENT INTEGRITY - OPERATING shall be demonstrated by:
a.
Verifying at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> that the pressures within the
-Shield Building annulus, the Auxiliary Building and the Fuel Building are less than or equal to 3.0, 0.00, and 0.00 indhes of vacuum water gauge, respectively, b.
Verifying at least once per 31 days that:
1.
All secondary containment equipment hatch covers are installed.
2.
The door in each access to the secondary containment is closed, except during normal entry and exit.
3.
All secondary containment penetrations not capable of being closed by OPERABLE secondary containment automatic isolation dampers and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic dampers / valves secured in position.
)
RIVER BEND - UNIT 1 3/4 6-48
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