ML20094B437
| ML20094B437 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 10/24/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Atlantic City Electric Co |
| Shared Package | |
| ML20094B441 | List: |
| References | |
| NPF-57-A-085 NUDOCS 9511010047 | |
| Download: ML20094B437 (13) | |
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 30806 4001
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PUBLIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY 1
j DOCKEI NO. 50-354 l
HOPE CREEK GENERATING STATION l
AMENDMENT TO FACILITY OPERATING LICENSE i
4 Amendment No. 85 l
License No. NPF-57 1
1 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found j
that:
i j
A.
The applications for amendment filed by the Public Service Electric
& Gas Company (PSE&G) dated November 30, 1994, and March 30, 1995, I
as supplemented by letter dated September 5,1995, complies.with the i
standards and requirements of the Atomic Energy Act of 1954, as i
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 i
Comission; i
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 l
in 10 CFR Chapter I; 1
D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have j
been satisfied.
i 2.
Accordingly, the license is amended by changes to the Technical i
Specifications as indicated in the attachment to this license amendment, j
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 i
l The Technical Specifications contained in Appendix A, as revised 1
through Amendment No.85, and the Environmental Protection Plan i
contained in Appendix B, are hereby incorporated into the license.
PSE&G shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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9511010047 951024 PDR ADOCK 05000354 P
3.
The license amendment is effective as of its date of issuance, to be implemented within 60 days.
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FOR THE NUCLEAR REGULATORY COMMISSION r
i J
. Stolz, Director i
P ject Directorate I-
{
D vision of Reactor Projects - I/II Office of Nuclear Reactor Regulation j
Attachment:
Changes to the Technical i
Specifications Date of Issuance: October 24, 1995
ATTACHMENT TO LICENSE AMENDMENT N0.85 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.
Remove Insert 3/4 3-1 3/4 3-1 3/4 3-6 3/4 3-6 3/4 3-9 3/4 3-9 3/4 3-10 3/4 3-10 3/4 3-26 3/4 3-26 3/4 3-27 3/4 3-27 3/4 3-32 3/4 3-32 3/4 3-38 3/4 3-38 B 3/4 3-1 B 3/4 3-1 B 3/4 3-2 B 3/4 3-2
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l 3/4.3 INSTRUMENTATION l
3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION i
I l
3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE.
i APPLICABILITY: As shown in Table 3.3.1-1.
ACTION:
a.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel (s) and/or that trip system in the tripped condi-tion
- within twelve hours. The provisions of Specification 3.0.4 are not applicable.
b.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, place at least one trip system ** in the tripped condition within one hour and take the ACTION required by Table 3.3.1-1.
SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1.1-1.
4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shall be demonstrated to be within its limit at least once per 18 months. Neutron detectors are exempt from response time testing.
Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip system.
4.3.1.4 The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 2 or 3 from OPERATIONAL CONDITION 1 for the Inter-mediate Range Monitors.
- An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or the ACTION required by Table 3.3.1-1 for that Trip Function shall be taken.
- If more channels are inoperable in one trip system than in the other, place the trip system with more inoperable channels in the tripped condition, except when this would cau.se the Trip Function to occur.
HOPE CREEK 3/4 3-1 Amendment No.85 l
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9 THIS PAGg INTENTIONALLY LEFT BLANK HOPE CREEK 3/4 3-6 Amendment No. 86
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s INSTRUMENTATION 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2.
l APPLICABILITY: As shown in Table 3.3.2-1.
ACTION:
With an isolation actuation instrumentation channel trip setpoint less a.
conservative than the value shown in the Allowable values column of Table 3.3.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With the number of OPERABLE channels less than required by the minimum OPERABLE channels per trip system requirement for one trip system, either
- 1) place the inoperable channel (s) in the tripped condition within a)
I hour for trip functions without an OPERABLE channel, b) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for trip functions common to RPS instrumentation, and c) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for trip functions not common to RPS intrumentation, or
- 2) take the ACTION required by Table 3.3.2-1.
The provisions of Specification 3.0.4 are not applicable.
With the number of OPERABLE channels less than required by the minimum c.
OPERABLE channels per trip system requirement for both trip systems,
- 1) place the inoperable chennel(s) in one trip system in the tripped condition within one hou;, and
- 2) a) place the inoperable channel (s) in the remaining trip system in the tripped condition within 1)
I hour for trip functions without an OPERABLE channel, 2) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for trip functions common to RPS instrumentation, and 3) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for trip functions not common to RPS instrumentation, or b) take the ACTION required by Table 3.3.2-1.
The provisions of Specification 3.0.4 are not applicable.
HOPE CREEK 3/4 3-9 Amendment No.85 I
,e INSTRUMENTATION SURVEILLANCE REQUIREMENTS 4.3.2.1 Each isolation actuation instrumentation channel shall be demonstrated OPERABLE by the perforinance of the CHANNEL CHECK, CHANNEL FUNCTICAEAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIODIS and at the frequencies shown in Table 4.3.2.1-1.
4.3.2.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
4.3.2.3 1he ISOLATION SYSTEM RESPONSE TIME of each isolation trip function shall be demonstrated to be within its limit at least once per 18 months.
l Radiation detectors are exempt from response time testing.
Each test shall l
include at least one channel per trip system such that all channels are tested at least once every N times 18 months, where N is the total number of redundant channels in a specific isolation trip system.
I b
HOPE CREEK 3/4 3-10 Amendment No.85 l
1 THIS PAGE INTENTIONALLY LEFT BLANK l
i HOPE CREEK 3/4 3-26 Amendment No.
85
l THIS PAGE INTENTIONALLY LEFT BLANK ROPE CREEK 3/4 3-27 Amendment No. 85
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INSTRUMENTATION 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION d
i 3.3.3 The emergency core cooling system (ECCS) actuation instrumentation channels shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set consistent with the values chown in the Trip Setpoint column of Table 3.3.3-2.
l f
APPLICABILITY: As shown in Table 3.3.3-1.
ACTION:
a.
With an ECCS actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of j
Table 3.3.3-2, declare the channel inoperable until the channel is I
restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip setpoint value.
b.
With one or more ECCS actuation instrumentation channels a
inoperable, take the ACTION required by Table 3.3.3-1.
SURVEILLANCE REQUIREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and a*. the frequencies shown in Table 4.3.3.1-1, 4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per is months.
4.3.3.3 The ECCS RESPONSE TIME of each ECCS trip function shall be l
demonstrated to be within the limit at least once per 18 months. Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific ECCS trip system.
HOPE CREEK 3/4 3-32 Amendment No.85 l
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i THIS PAGE INTENTIONALLY LEFT BLANK l
HOPE CREEK 3/4 3-38 Amendment No.85
i 3/4.3 ~ INSTRIJMENTATION RASES 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION The reactor protection system automatically initiates a reactor scram to:
- a. Preserve the integrity of the fuel cladding,
- b. Preserve the integrity of the reactor coolant system.
- c. Minimize the energy which must be adsorbed following a loss-of-coolant accident, and
- d. Prevent inadvertent criticality.
This specification provides the limiting conditions for operation necessary to preserve the ability of the system to perform its intended function even during periods when instrument _ channels may be out of service because of main-tenance.
When necessary, one channel may be made inoperable for brief intervals to conduct required surveillance.
l The reactor protection system is made up of two independent trip systems.
There are usually four channels to monitor each parameter with two channels in each trip system.
The outputs of the channels in a trip system are combined in~a logic so that either channel will trip that trip system. The tripping of both trip systems will produce a reactor scram.
The system meets the intent of IEEE-279 for nuclear power plant protection systems.
Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordar.ca with NEDC-30851P, " Technical Specification Improvement Analyses 1or BWR Reactor Protection System," as approved by the NRC and documented in the SER (letter to T. A. Pickens from A. Thadani dated July 15, 1987). The bases for the trip settings of the RPS are discussed in the bases for Specification 2.2.1.
The measurement of response time at the specified frequencies provides assurance that the protective functions associated with each channel are com-pleted within the time limit assumed in the safety analyses. No credit was taken for those channels with response times indicated as not applicable, l
R sponse time may be demonstrated by any series of sequential, overlapping or total channel test measurement, provided such rests demonstrate the total channel. response time as defined. Sensor response time verification may be demonstrated by either (1) inplace, onsite or offsite test measurements, or (2) utilizing replacement sensors with certified response times. Selected sensor response time testing requirements were eliminated based upon NEDO-32291, " System Analyses for Elimination of Selected Response Time Testing Requirements," as approved by the NRC and documented in the SER (letter to K.A. Pinelli from Bruce A. Boger, dated December 28, 1994).
HOPE CREEK B 3/4 3-1 Amendment No.85 I
a e
e INSTPUMENTATION BASES 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION This specification ensures the effectiveness of the instrumentation used to mitigate the consequences of accidents by prescribing the OPERABILITY trip setpoints and response times for isolation of the reactor systems.
Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with NEDC-30851P-A, Supplement 2, " Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation i
Common to RPS and ECCS Instrumentation," and NEDC-31677P-A, " Technical Specification Improvement Analysis for BWR Isolation Actuation
)
Instrumentation." The safety evaluation reports documenting NRC approval of j
NEDC-30851P-A, Supplement 2 and NEDC-31677P-A are contained in letters to D.N.
I Grace from C.E. Rossi dated January 6, 1989 and to S.D. Floyd from C.E. Rossi dated June 18, 1990.
When necessary, one channel may be inoperable for brief intervals to conduct required surveillance. Some of the trip settings may have tolerances explicitly stated where both the high and low values are critical and may have a substantial effect on safety. The setpoints of other instrumentation, where only the high or low end of the setting have a direct bearing on safety, are established at a level away from the normal operating r= ge to prevent inadvertent actuation of the systems involved.
Except for the MSIVs, the safety analysis does not address individual sensor response times or the response times of the logic systems to which the sensors are connected. Selected sensor response time testing requirements were eliminated based upon NEDO-32291, " System Analyses for Elimination of Selected Response Time Testing Requirements," as approved by the NRC and documented in the SER (letter to R. A. Pinelli from Bruce A. Boger, dated December 28, 1994).
Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable value is acceptable on the basis that the difference between each Trip setpoint and the Allowable Value is an allowance for instrument drift specifically allocated for each trip in the safety analyses.
3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION The emergency core cooling system actuation instrumentation is provided to initiate actions to mitigate the consequences of accidents that are beyond the ability of the operator to control. This specification provides the OPERABILITY requirements, trip setpoints and response times that will ensure effectiveness of the systems to provide the design protection. ECCS actuation instrumentation is eliminated from response time testing requirements based on NEDO-32291, " System Analyses for Elimination of Selected Response Time Testing Requirements," as approved by the NRC and documented in the SER (letter to R.A. Pinelli from Bruce A. Boger, dated December 28, 1994). Specified HOPE CREEK B 3/4 3-2 Amendment No.85 l
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