ML20070B785
| ML20070B785 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 01/25/1991 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070B789 | List: |
| References | |
| TAC-77565, NUDOCS 9102040066 | |
| Download: ML20070B785 (11) | |
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'o UNITED STATES g
NUCLEAR REGULATORY COMMISSION n
1 MSHINGTON, D C. 20556 i
CONSUMERS POWER COMPANY PALISADES PLANT DOCKET NO. 50-255 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No.134 License No. DPR-20 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated August 21, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (theAct),andtheCommission'srulesandregulationssetforth in 10 CFR Chapter I; D.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
Thereisreasonableassurance_(1)thattheactivitiesauthorized 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.9f 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 1icense is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B. of Provisional Operating License No. DPR-20 is hereby amended to read as follows:
9102040066 910125 PDR ADOCK 05000255 P
2 Technical Specifications a
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.194, are hereby incorporated in the license. The licensee shalT operate the facility in accordance with the Technical Specifications.
j 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMIS$10H W
L. B. Marsh, Director Project Directorate 111 1 o
Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 25, 1991 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 134 PROVISIONAL OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255
'4 Revise Appendix A Technical Saecifications by removing the pages identified below and inserting the attacled pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT iv-iv 3-lb 3-lb 3-Ic 3-Ic 3-2 3-2 3-3 3-3 3-22 3-22 4-24 4-24 4-24a 4-24a s
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PALISADES PLANT TECHNICAL SPECITICATIONS TABLE OF CONTENTS - APPENDIX A SECTION DESCRIPTION PAGE NO 4.0 SURVEILLANCE REQUIREMENTS 4-1 4.1 INSTRUMENTATION AND CONTROL 4 -1 4.1.1 Overpressure Protection Systems 4-1 Table 4.1.1 Minimum Frecuencies for Checks, Calibrations and Testing of Reactor Protective System 4-3 Table 4.1.2 Minimum Frecuencies for Checks, Calibrations and Testing of Engineered Safety Feature Instrumentation Controls 4-6 Table 4.1.3 Minimum Frecuencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls 4-10 4.2 EQUIPMENT AND SAMPLING TESTS 4-13 Table 4.2.1 Minimum Frecuencies for Sampling Tests 4-14 Table 4.2.2 Minimum Frecuencies for Ecuipment Tests 4-15 Table 4.2.3 HEPA Filter and Charcoal Adsorber Systems 4-15e 4.3 SYSTEMS SURVEILLANCE 4-16 Table 4.3.1 Primary Coolant System Pressure Isolation Valves 4-19 Table 4.3.2 Miscellaneous Surveillance Items 4-23 4.4 Deleted 4-24 /
4.5 CONTAINMENT TESTS 4-25 4.5.1 Integrated Leakage Rate Tests 4-25 4.5.2 Local Leak Detection Tests 4-27 4.5.3 Recirculation Heat Removal Systems 4-28a 4.5.4 Surveillance for Prestressing System 4-29 4.5.5 End Anchorage Concrete Surveillance 4-32 4.5.6 Containment Isolation Valves 4-32 4.5.7 Deleted 4-32a 4.5.8 Domo Delamination Surveillance 4-32a 4.6 SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEMS TESTS 4-39 4.6.1 Safety Injection System 4-39
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4.6.2 Contsinment Spray System 4-39 4.6.3 Pumpe 4-39 4.6.4 Valves (Deleted) 4-40 4.6.5 Containment Air Cooling System 4-40 4.7 EMERGENCY POWER SYSTEM PERIODIC TESTS 4-42 4.7.1 Diesel Generators 4-42 4.7.2 Station Batteries 4-42
4.7.3 Emergene
Lighting 4-43 4.8 MAIN STEAM STOP VALVES 4-44 4.9 AUXILIARY FEEDWATER SYSTEM 4-45 4.10 REACTIVITY ANOMALIES 4-46 4.I1 RADIOLOGICAL ENVIRONMENTAL MONITORING 4-47 Table 4.11-1 Radiological Environmental Monitoring Program 4-49 Table 4.11-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 4-56 iv Amendment No. 37, 48, 63, 67, l
68, 85, 108, 128/ 134 l
1, TSP 0790-0371A-NLO2
3,1 PRIMARY COOLANT SYSTEM 6
Applicability Applies to the operable status of the primary coolant system.
p4eetive To specify certain ecnditions of the primary coolant system which must be met to assure safe reactor operation.
Specification; 3.1.1 Operable Components a.
At least one primary coolant pump or one shutdown cooling pump with a flow rate greater than or coual to 2810 gpm shall be in operation whenever a change is being made in the boron concentration of the primary coolant and the plant is operating in cold shutdown or above, except during an emer;;ency loss of coolant flow situation. Under these ci:cumstances, the boron concentration may be increased with no primary coolant pumps or shutdown cooling pumps running, b.
Four p imrcy coolant pumps shall be in operation whenever the react
- is oper ted above hot shutdown, with the following exception:
Before removing a pump from service, thermal power shall be 7y reduced as specified in Table 2.3.1 and appropriate corrective I$ 2 action implemented. With one pump out of service, return the pump to service within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (return to four-pump operation) or be in hot shutdown (or below) with the reactor tripped (from n
the C-06 panel, opening the 42-01 and 42-02 circuit breakers) within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Start-up (above hot shutdown) with less than four pumps is not permitted and power operation witi, less than three pumps is not permitted, c.
The measured four primary coolant pumps operating reactor 6
vessel flow shall be 124.3 x 10 lb/hr or greater, when corrected to 532'F.
d.
Both steam generators shall be capable of performing their here transfer function whenever the average temperature of the primary coolant is above 325'F.
e.
Deleted
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3-lb Amendment No 31, 85, IIS, 179,134 tsp 0790-0371A-NLO2
i 3.1-PRIMARY-COOLANT SYSTEM (Continued) 3.1.1 Operable Components (Continued)
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f.
Nominal pr', mary system operation pressure shall not exceed 2100 psia.
g.
The reactor inlet temperature (indicated) shall not exceed the value given by the following ecuation at steady state power operation:
T 5 543.3 +.0575(P-2060) + 0.00005(P-2060)**2 + 1.173(W-120) -
inlet
.010 2 (W-120)*
- 2 Where T
= reactor inlet temperature-in F*
inlet P = nominal operating pressure in psia 6
W = total recirculating mass flow in 10 lb/h corrected to the operating temperature conditions.-
When the ASI exceeds the limits specified in Figure 3.0, within 15-minutes, initiate corrective actions to restore the ASI to the acceptable region. Restore the ASI to acceptable values within one hour or be at less than 70% of rated power within the following two hours.
If the measured primary coolant system flow rate is greater than'130 M lbm/hr, the maximum inlet temperature shall be less than or ecual to the T LCO at 130 M lbm/hr.
Inlet 3-Ic Amendment No 31, 51, 85, !!7. !!8, 134 TSP 0790-0371A-NLO2
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J 3.1 PRIMARY COOLANT SYSTEM (contd)
Basis (Contd)
The FSAR safety analysis was performed assuming four primary coolant pumps-were operating for accidents that occur during reactor operation. Therefore, reheter startup above hot shutdown is not permitted unless all four primary coolant pumps are operating.
Operation with three primary coolant pumps-is permitted for a limited time to allow the restart of a stopped pump or for reactor internals vibration monitoring and tcsting.
Reouiring the plant to be in hot shutdown with the reactor tripped from the C200 panel, opening the 42-01 and 42-02 circuit breakers, assures an inadvertent rod bank withdrawal vill not be initiated by the control room operator. Both steam generators are recuired to be operable whenever the temperature of the primary coolant is greater than the design temperature of the shutdown cooling system to assure a redundant hear removal system for the reactor.
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The transient analyses were performeg assuming a vessel flow at hot zero power (532*F) of 124.3 x 10 lb/hr minus 6% of account for flow measurement uncertainty and core flow bypass. A DNB analysis was performed in a parametric f ashion to determine. the core inlet temperature as.a function of pressure ard flow for which the minimum DNBR is eoual to 1.17.
This analysis includes-the following uncertainties and allowances: 2% of rated power for power l
3-2 Amendment No 20, 31. TIS,131,134 I
tsp 0790-0371A-NLO2 l-
.m 3.1 PRIMARY COOLANT SYSTEM (Cont'd)
Basis'(Cont'd) measurement; 10'.06 for ASI measurement; 250 psi for pressurizer pressure; 17'T for inlet temperature; and 3% measurement and 3%
bypass for core flow.
In addition, transient biases were included in.
the derivatiop49 the following ecuation for l'aiting reactor inlet f
temperature:
Tinlet 5 543.3 +.0575(P-2060) + 0.00005(P-2060)**2 + 1.173(W-120) -
.0102(W-120)**2 The limits of validity of this ecuation are:
1800 5 Pregsure 5 2200 psia 6
100.0 x 10 5 Vessel Flow 5 130 x 10 lb/h ASI as shown in Figure 3.0 With measured primary coolant system flow rates > 130 M lbm/hr, limiting the maximum allowed inlet temperature to the T,1,g LCO at 7
130 M lbm/hr increases the margin to DNB for higher PCS flow rates.
The Axial Shape Index alarm channel is being used to monitor the ASI to ensure that the assumed axial power profiles used in the development of the inlet temperature LCO bound measured axial power
-profiles.
The sr;oal representing core power (Q) is the auctieneered higher of the neutron flux power and the Delta-T power.
The measured ASI calculated from the excore detector signals and adjusted for shape annealing (Y,) and the core power constitute an ordered pair (Q,Y,).
An alarm Aignal is activated before the ordered pair exce&d the boundaries specified in Figure 3.0.
The recuirement that the steam generator temperature be 5 the PCS temperature when forced circulation is initiated in the PCS ensures that an energy addition caused by heat transferred from
-the-secondary system to the PCS will not occur. This recuirement applies only to the initiation of forced circulation (the start of the first primary coolant pump) when the PCS cold leg
. temperature is < 430'F.
However, analysis (Reference 6) shows that under limited conditions when the Shutdown Cooling System
-is isolated from the PCS. forced circulation may be initiated when the steam generator temperature is higher than the PCS cold leg temperature.
References (1) Updated TSAR, Section 14.3.2.
(2) Updated FSAR, Section 4.3.7.
(3) Deleted
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(4)' ANT-87-150(NP), Volume 2, Section 15.0.7.1 (5) ANT-88-108 (6) Consumers Power Company Engineering Analysis EA-A-NL-89-14-1 3-3 Amendment No 31, fl.117,118,131; 134 TSP 0790-0371A-NLO2
3.1 PRIMARY COOLANT SYSTDi (contd)
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The steam generator tube leakage limit ensures that the dosage
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contributed from the tube leakage will be limited to a small
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fraction of Part 100 limits in the event of a steam generator tube
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rupture or steam line break. The leakage. limit also ensures that-
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steam generator tube integrity is maintained in the event of a main
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steam-line1 rupture or under LOCA conditions.
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Operation during short periods of time when the leakage measurement sensitivity is reduced is provided for by an added allowance to the leakage limit. Leakage limits are not reoutred when the plant is not at power.
References
/1) 'FSAR. Amendment 15 Question 4.3.
(2) FSAR, Section 11. Table 11-6.
3-22 Amendment No 20134 j
. TSP 0790-0371A-NLO2
4.4 Deleted l
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i 4-24 Amendment No. 25,134 TSP 0790-0371A-NLO2
4,4
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4-24a Amendment No. 134 I
TSP 0790-0371A-NLO2