ML20129E476
| ML20129E476 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 09/30/1996 |
| From: | Polich T NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20129E480 | List: |
| References | |
| NUDOCS 9610030179 | |
| Download: ML20129E476 (13) | |
Text
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4 UNITED STATES E
NUCLEAR REGULATORY COMMISSION I
f WASHINGTON, D.C. 20666 00M TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 1 4
DOCKET NO. 50-445 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 i
License No. NPF-87 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Texas Utilities Electric Company (TU Electric, the licensee) dated July 31, 1996 (TXX-96433),
complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and i
regulations set forth in 10 CFR Chapter I; i
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B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of j
the Comission; 4
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 Comission's regulations; a
D.
The issuance of this license amendment will not be inimical to the i
comon defense and security or to the health and safety of the public; and 1
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all appilcable requirements have l
been satisfied.
E.
Accordingly, the license is amended by changes to the Technical s
Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-87 is hereby amended to read as follows:
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9610030179 960930 PDR ADOCK 05000445 P
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. 2.
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 52, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Timothy J. Polich, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV i
j Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical l
Specifications Date of Issuance: September 30, 1996 4
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION "g
a WASHINGTON, D.C. 20066-0001
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i TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 2 4
DOCKET NO. 50-446 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 38 License No. NPF-89 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Texas Utilities Electric Company (TV Electric, the licensee) dated July 31, 1996 (TXX-96433),
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, as amended, the provisions of the Act, and the rules and 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 activit'ies will be conducted in compliance with the Commission's regulations; D.
The issuance of this license 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 Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-89 is hereby amended to read as follows:
l (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 38, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.
TU Electric shall operate the facility in accordance with the l
Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMISSION
&/0D Timothy J. Polich, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 30, 1996 i
ATTACHMENT TO LICENSE AMENDMENT NOS. 52 AND 38 FACILITY OPERATING LICENSE NOS. NPF-87 AND NPF-89 i
DOCKET NOS. 50-445 AND 50-446 4
Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 2-2 2-2 2-9 2-9 2-10 2-10 2-11 2-11 6-11 6-11 i
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l 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS l
i 2.1 SAFETY LIMITS i
REACTOR CORE 2.1.1 The combination of THERMAL POWER, pressurizer pressure, and the highest operating loop coolant temperature (T,) shall not exceed the limits shown in Figure 2.1-1.
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APPLICABILITY: MODES I and 2.
ACTION:
Whenever the point defined by the combination of the highest operating loop average temperature and THERMAL POWER has exceeded the appropriate pressurizer 4
pressure line, be in HOT STAND 8Y within I hour, and comply with the require-ments of Specification 6.7.1.
f REACTOR COOLANT SYSTEM PRESSURE i
2.1.2 The Reactor Coolant System pressure shall not exceed 2735 psig.
2 APPLICABILITY: MODES 1, 2, 3, 4, and 5.
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l ACTION:
MODES 1 and 2:
Whenever the Reactor Coolant System pressure has exceeded 2735 psig, be in HOT STAND 8Y with the Reactor Coolant System pressure within its limit within I hour, and comply with the requirements of Specification 6.7.1.
MODES 3, 4 and 5:
Whenever the Reactor Coolant System pressure has exceeded 2735 psig, reduce the Reactor Coolant System pressure to within its limit within 5 minutes, and comply with the requirements of Specification 6.7.1.
COMANCHE PEAK - UNITS 1 AND 2 2-1
Unit 1 R :ctor C re Safety Limits 670 l Unacceptable :
l N
i Operation j N
650 N
2385 psig 640 P = 2235 psig l
E630 l
T P = 1985 psig P = 1845 psig 610 000 l
N h
Acceptable ~
j Operation l 590 680 0
20 40 80 80 100 120 Percent of Rated Thermal Power FIGURE 2.1-la UNIT 1 CEACT0_R CORE SAFETY _ LIMITS COMANCHE PEAK - UNITS 1 AND 2 2-2 Unit 1 - Amendment No. 14 31,52 7
Unit 2 - Amendment No. 7,38
TABLE 2.2-1 (Continued)
TABLE NOTATIONS NOTE 1: Overtemperature N-16 2[1+rs T,-T,*] + K3 (P-P') - f, (aq)
N K -K i
a Measured N-16 Fawer by ion chambers, Where:
N Cold leg temperature,
- F, T,
T*
560.5*F for Unit 1, 560.8'F for Unit 2 - Reference T, at RATED THERMAL POWER, 1.150, K,
0.0173/*F for Unit 1 l
K 2
0.0138/*F for Unit 2 1+rs The function generated by the lead-lag controller for i
1+Ts2 T, dynamic compensation, Time constants utilized in the lead-lag controller for r,72 i
210 s, and r2 s 3 s, T,, ti 0.000890/psig for IJnit 1 l
K 3
0.000720/psig.for Unit 2 i
COMANCHE PEAK - UNIT 1 AND 2 2-9 Unit 1 - Amendment No. 11,21,4^,52 Unit 2 - Amendment No.
7 35, 38 7
TABLE 2.2-1 (Continued)
JABLE NOTATIONS (Continued)
NOTE 1:
(Continued)-
P Pressurizer pressure, psig,
=
P' 2
2235 psig (Nominal RCS operating pressure),
Laplace transform operator, s,
S and f,(aq) is a function of the indicated difference between top and bottom halves of detectors of the power-range neutron ion chambers; with gains to be selected based on measured instrument response during plant STARTUP tests such that:
For Unit 1 (i) for q - q, between -65% and +4.6%, f (aq) - 0, where q RATED,THERhAL POWER.in the top and bottom halves of the, and q, are percent l
i core respectively, and q, + q, is total THERMAL POWER in percent of RATED THERMAL POWER, (ii) for each percent that the magnitude of q - q, exceeds -65%, the N-16 Trip Setpoint shall be automatically reduced by 0.~0%* of its value at RATED l
. THERMAL POWER, and (iii) for each percent that the magnitude of q - q, exceeds +4.6%, the N-16 Trip Setpoint shall be automatically reduced by 3.04% of its value at RATED THERMAL POWER.
- No setpoint reduction is required for the span of the al indication.
l COMANCHE PEAK - UNIT 1 AND 2' 2-10 Unit 1 - Amendment No. 4hM,52 Unit 2 - Amendment No.
7,38,
TABLE 2.2-1 (Continued)
TABLE NOTATIONS (Continued)
NOTE 1:
(Continued)
For Unit 2 i
RATED,THERML POWER in the top and bottom halves of the, and q, are percent for q - g between -65% and +2.5%, f,(aq) = 0, where q
.(1) i core respectively, i
and q, + q, is total THERMAL POWER in percent of RATED THERMAL POWER, (ii) for each percent that the magnitude of q - g exceeds -65%, the N-16 Trip
' Setpoint shall be automatically reduced by 1.86% of its value at RATED THERMAL POWER, and (iii) for each percent that the magnitude of q - q, exceeds +2.5%, the N-16 Trip 1
Setpoint shall be automatically reduced by 1.65% of its value at RATED THERMAL POWER.
NOTE 2:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 3.64% l I
of span for Unit I or 1.88% of span for Unit 2.
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COMANCHE PEAK - UNIT I AND 2 2-11 Unit 1 - Amendment No. 14,21,41,4?,52 Unit 2 - Amendment No.
7,27,35, 38
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ADMINISTRATIVE CONTROLS i
CORE OPERATING LIMITS REPORT (Continued) i Reference 18) is for Unit 2 only:
I 18). WCAP-9220-P-A, Rev. 1, " WESTINGHOUSE ECCS EVALUATION MODEL-1981 Version", February 1982 (W Proprietary).
j 19). RXE-94-001-A, " Safety Analysis of Postulated Inadvertent Boron j
Dilution Event in Modes 3, 4, and 5," February 1994.
(Methodology j
for Specifications 3/4.1.1.1,3/4.1.1.2,3/4.1.2.2,3/4.1.2.4,and j
3/4.1.2.6 - Shutdown Margin.)
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20.) RXE-95-001-P, "Small Break Loss of Coolant Accident Analysis j
Methodology," December 1995.
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6.9.1.6c The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as SHUTDOWN MARGIN, and transient and j
accident analysis limits) of the safety analysis are met.
6.9.1.6d The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or. supplements thereto, shall be provided upon issuance, for each reload 4
cycle, to the NRC Document Control Desk with copies to the Regional i
Administrator and Resident Inspector.
SPECIAL REPORTS 6.9.2 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period speci -
fied for each report.
6.10 NDT USED i
6.11 NOT USED 6.12 HIGH RADIATION AREA i
j 6.12.1 Pursuant to paragraph 10 CFR 20.1601(c), in lieu of the " control 1
device" or " alarm. signal" required by paragraph 10 CFR 20.1601(a), each high radiation area, as defined in 10 CFR 20, in which the intensity of radiation is equal to or less than 1000 mrem /h at 30 cm (12 in.) from the radiation i
source er from any surface which the radiation penetrates shall be barricaded j
and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).
Indi-viduals qualified in radiation protection procedures (e.g., Radiation Protec-1 tion Technician) or personnel continuously escorted by such individuals may be i
exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with dose rates equal.to or less than i
1000 mres/h, provided they are otherwise following plant radiation protection
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procedures for entry into such high radiation _ areas. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
COMANCHE PEAK - UNITS 1 AND 2 6-11 Unit 1 - Amendment No. 21,42,44,50,52 l
Unit 2 - Amendment No.
7,20,30,35,38 i
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HICH RADIATION AREA fcontinuad)
A radiation monitoring device which continuously indicates tha a.
radiation dose rate in the area; or i
l b.
A radiation monitoring device which continuously integrates the j
radiation dose rate in the area and alarms when a preset integrated i
dose is received. Entry into such areas with this monitoring device i
may be made after the dose rate levels in the area have been estab-l lished and individuals have been made knowledgeable of them; or 4
j c.
An individual qualified in radiation protection procedures with a i
radiation dose rate monitoring device, who is responsible for pro-l viding positive control over the activities within the area and shall perforis. periodic radiation surveillance at the frequency 1
i specified by the RWP.
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6.12.2 In. addition to the requirements of Specification 6.I'2.1, areas acces-sible to individuals with radiation levels greater than 1000 ares /h at 30 cm j
(12 in.) but less than 500 rads in one hour at one meter from the radiation l
source or from any surface which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be i
maintained under the administrative control of the Shift Manager on duty l
1 and/or radiation protection supervision. Doors shall remain locked except l
during periods of access by individuals under an approved RWP which shall specify the dose rate levels in the immediate work areas and the maximum i
allowable stay time for individuals in that area.
In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by individuals qualified in radiation j
protection procedures to provide positive exposure control over the activities being performed within tha area.
For isolated high radiation areas accessible to individuals with radiation levels of greater than 1000 ares /h at 30 cm but less than 500 rads in one hour at one meter that are located within large areas, such as PWR containment, I
where no enclosure exists for purposes of locking, and where no enclosure can i
be reasonably constructed around the isolated area, that isolated area shall
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be barricaded, conspicuously posted, and a flashing light shall be activated j
as a warning device.
6.13 NOT USED l
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6.14 0FFSITE DOSE CALCULATION MANUAL (CDCM)
Changes to the 00CM:
a.
Shall be documented and records of reviews performed shall be retained for the duration of the unit Operating License. This l
documentation shall contain:
1)
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and COMANCHE PEAK - UNITS 1 AND 2 6-12 Unit 1 - Amendment No. !!,?:,44,50 Unit 2 - Amendment No. 7,2*,30,36