ML20237G667
| ML20237G667 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/17/1987 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20237G668 | List: |
| References | |
| NUDOCS 8708240182 | |
| Download: ML20237G667 (16) | |
Text
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'o UNITED STATES NUCLEAR REGULATORY COMMISSION
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\\... f PUBLIC SERVICE ELECTRIC & GAS COMPANY i
ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 8 License No. NPF-57 1.
The Nuclear Regulatory Commissinn (the Commission or the NRC) has found that:
l A.
The application for amendment filed by the Public Service Electric &
Gas Company (PSE&G) dated May 22, 1987, as supplemented June 30, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance: (1) 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 Comission's regulations set forth in 10 CFR Chapter I; 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 applicabig requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Tecnnical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-57 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.
8, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PSE&G shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8708240182 870817 PDR ADOCK 05000354 p
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This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMtilSSION
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i Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical l
Specifications
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FOR THE NUCLEAR REGULATORY COMMISSION l
l Walter R. Butler, Dire'ctor i
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Attachment:
Changes to the Technical j
Specifications Date of Issuance: August 17, 1987 1
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i ATTACHMENT TO LICFNSE AMENDMENT NO. ' 8 i
FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overleaf page(s) provided I
to maintain document completeness.*
i Remove Insert 2-3*
2-3*
2-4 2-4 2-5 2-5 l
3/4 3-11*
3/4 3-11*
l 3/4 3-12 3/4 3-12 3/4 3-15*
3/4 3-15*
3/4 3-16 3/4 3-16 3/4 3-16a 3/4 3-21*
3/4 3-21*
3/4 3-22 3/4 3-22 1
3/4 3-25 3/4 3-25 3/4 3-26*
3/4 3-26*
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m SAT!T' LIMITS AND LIMITIN3 SAFET) SYSTEM SETTINGS 2.2 LIMITING SArg73 SyS7EM SETTINGS REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS 2.2.1. The reactor protection system instrumentation setpoints shall be set consistent with the Trip Setpoint values.shown in Table 2.2.1-1.
ADFLICABILITY: As shown in Table 3.3.1-1.
ACT]CN:
With a reactor protection system instrumentation setpoint less conservative than the value she.'n in the Allowable Values column of Table 2.2.1-1, declare the channel inoperable and apply the applicable ACTION statement requirement of Spe:ification 3.3.1 until the channel is restored to OPERABLE status witn its setpoint acjustec consistent with the Trip 5etpoint value.
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TABLE 3.3.2-1 (Continued) l ISOLATION ACTUATION INSTRUMENTATION l
ACTION ACTION 20 Be in at least HOT SHUTOOWN within 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 next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 21 Be in at least STARTUP with the associated isolation valves closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at'least HOT SHUTDOWN within 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 next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 22 Be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 23 Close the affected system isolation valves within one hour and declare the affected system inoperable.
ACTION 24 Restore the manual initiation function to OPERABLE status within 1
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTOOWN within the next 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 />.
ACTION 25 Restore the manual initiation function to OPERABLE status within
)
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or close the affected system isolation valves within the next hour and declare the affected system inoperable.
ACTION 26 Establish SECONDARY CONTAINMENT INTEGRITY with the Filtration, Recirculation and Ventilation System (FRVS) operating within one hour.
ACTION 27 -
Lock the affected system isolation valves closed within one hour and declare the affected system inoperable.
ACTION 28 Place the inoperable channel in the tripped condition or close the affected system isolation valves within one hour and declare the affected system inoperable.
ACTION 29 Place the inoperable channel in the tripped condition or establish SECONDARY CONTAINMENT INTEGRITY with the Filtration, Recirculation, and Ventilation System (FRVS) operating within one hour.
NOTES When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with a potential for' draining the reactor vesrel.
When any turbine stop valve is greater than 90% open and/or when the key-locked bypass switch is in the Norm position.
Refer to Specification 3.1.5 for applicability.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test, with reactor power at greater than 22% of RATED THERMAL POWER, the normal full power radiation background level and associated trip setpoints may be I
changed based on a calculated value of the radiation level expected during the test. The background radiation level.and associated trip setpoints may be adjusted during the test program based on either calculations or measure-ments of actual radiation levels resulting from hydrogen injection. The background radiation level shall be determined ind the associated trip l
setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re establishing normal radiation I
levels after completion of the hydrogen injection test or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor power levels below 22% of RATED THERMAL POWER, while these functions are required to be OPERABLE.
l (a) A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for re-l quired surveillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is l
monitoring that parameter.
l (b) Also trips.and isolates the mechanical vacuum pumps.
(c) Also starts the Filtration, Recirculation and Ventilation System (FRVS).
i HOPE CREEK 3/4 3-16 Amendment No.
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. TABLE 3.3.2-1 (Continued)
ACTION (Continued)
(d) Refer to Table 3.3.2-1 table notation for the listing of which valves in an actuation group are closed by a particular isolation signal.
Refer to Tables 3.6.3-1 and 3.6.5.2-1 for the listings of all valves within an actuation group.
(e) Sensors arranged per valve group, not per trip system.
(f) Closes only RWCU system isolation valve (s) HV-F001 and HV-F004.
(g) Requires system steam supply pressure-low coincident with drywell pressure-high to close turbine exhaust vacuum breaker valves.
(h) Manual isolation closes HV-F008 only, and only following manual or automatic initiation of the RCIC system.
l (i) Manual isolation closes HV-F003 and HV-F042 only, and only following manual or automatic initiation of the HPCI system.
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TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds)#
1.
PRIMARY CONTAINMENT ISOLATION a.
1)
Low Low, Level 2 NA j
l 2)
Low Low Low, Level I NA i
l b.
Drywell Pressure - High NA c.
Reactor Building Exhaust Radiation - High NA d.
Manual Initiation NA 2.
SECONDARY CONTAINMENT ISOLATION a.
Reactor Vessel Water Level-Low Low, Level 2 NA b.
Drywell Pressure - High NA i
c.
Refueling Floor Exhaust Radiation -
-< 4.0 High(b) d.
Reactor Building Exhaust
< 4.0 3
Radiation - Higb(b) e.
Manual Initiation NA 3.
MAIN STEAM LINE ISOLATION Reactor Vessel Water Level - Low Low Low, a.
Level 1
< 1.0*/< 13(3),,
Main Steam Line Radiation - High, Higb(a)(b-)
7 1.0*/7 13((a))w.
a,,
i D.
c.
Main Steam Line Pressure - Low
~ 1.0*/7 13 d.
Main Steam Line Flow-High 50.5*/513(*)*n
,l e.
Condenser Vacuum - Low NA
'l f.
Main Steam Line Tunnel Temperature -.High NA g.
Manual Initiatien NA 4.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
RWCU A Flow - High NA b.
RWCU A Flow - High, Timer NA c.
RWCU Area Temperature - High NA d.
RWCU Area Ventilation A Temperature - High NA e.
SLCS Initiation NA f.
Reactor Vessel Water Level - Low Low, Level 2 NA g.
Manual Initiation NA 5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a.
RCIC Steam Line o Pressure (Flow) - High NA b.
RCIC Steam Line A Pressure (Flow) - High, Timer NA c.
RCIC Steam Supply Pressure - Low NA d.
RCIC Turbine Exhaust Diaphragm Pressure - High NA HOPE CREEK 3/4 3-26 j
I N
"