ML20247E774
| ML20247E774 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 09/05/1989 |
| From: | Thoma J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247E778 | List: |
| References | |
| NUDOCS 8909150376 | |
| Download: ML20247E774 (17) | |
Text
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UNITED STATES g -
NUCLEAR REGULATORY COMMISSION 7n
- E WASHINGTON, D. C. 20555
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CONSUMERS POWER COMPANY PALISADES PLANT DOCKET NO. 50-255 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 128 License No. DPR-20 1.
The Nuclear Regulatory Comission'(the Comission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee)datedSeptember 15, 1988 complies with the standards and requirements of the Atomic Energy.Act of 1954, as amended (the Act).-and the Comission'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 Commission's regulations; 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 been satisfied.
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2.
Accordingly, the license'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
Technical Specifications The Technical Specifications contained.in Appendices A and B, as revised through Amendment No.128, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the'date of its issuance and shall be implemented not later than October'16,1989.
FOR THE NUCLEAR REGULATORY COMMISSION J n Thoma, Acting Director Project Directorate 111-1 Division of Reactor Projects - III, IV, V
& Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications
'Date of Issuance: September 5, 1989
ATTACHMENT TO LICENSE AMENDMENT NO.128 PROVISIONAL OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by
.the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT i
i iv iv I-4 1-4 1-5 1-5 3-40 3-40 3-40a 3-40a 3-40b 3-40c 3-40d 3-40e 3-40f 3-40g 4-32 4-32 4-32a 4
PAL 2SADES PLANT TECHNICAL SPECIF8 CATIONS TABLE OF CONTENTS - APPENDIX A
~
SECTION DESCRIPTION PAGE NO 1.0 DEFINITIONS 1-1 1.1 REACTOR OPERATING CONDITIONS 1-1 1.2 PROTECTIVE SYSTEMS 1-3 1.3 INSTRUMENTATION SURVEILLANCE 1-3 1.4 MISCELLANEOUS DEFINITIONS 1-4 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2-1 2.1 SAFETY LIMITS - REACTOR CORE 2-1 2.2 SAFETY LIMITS - PRIMARY COOLANT SYSTEM PRESSURE 2-3 2.3 LIMITING SAFETY SYSTEM SETTINGS - REACTOR PROTECTIVE SYSTEM 2-4 Table 2.3.1 Reactor Protective System Trip Setting Limits 2-5 3.0 LIMITING CONDITIONS FOR OPERATION 3-1 3.0 APPLICABILITY 3-1 3.1 PRIMARY COOLANT SYSTEM 3-Ib 3.1.1 Operable Components 3-lb Figure 3-0 Reactor Inlet Temperature vs Operating Pressure 3-3a 3.1.2 Heatup and Cooldown Rates 3-4 Figure 3-1 Pressure - Temperature limits for Heatup 3-9 Figure 3-2 Pressure - Temperature limits for Cooldown 3-10 Figure 3-3 Pressure - Temperature Limits for Hydro Test 3-11 3.1.3 Minimum Conditions for Criticality 3-12 3.1.4 Maximum Primary Coolant Radioactivity 3-17 3.1.5 Primary Coolant System Leakage Limits 3-20 3.1.6 Maximum Primary Coolant Oxygen and Halogens concentrations 3-23 3.1.7 Primary and Secondary Safety Valves 3-25 1
3.1.8 Overpressure Protection Systems 3-25a i
3.2 CHEMICAL AND VOLUME CONTROL SYSTEM 3-26 i
3.3 EMERGENCY CORE COOLING SYSTEM 3-29 3.4 CONTAINMENT COOLING 3-34 3.5 STEAM AND TEEDWATER SYSTEMS 3-38 I
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3.6 CONTAINMENT SYSTEM 3-40 Table 3.6.1 Containment Penetrations and Valves 3-40b /
3.7 ELECTRICAL SYSTEMS 3-41 3.8 REFUELING OPERATIONS 3-46 3.9 EFFLUENT RELEASE (DELETED) 3-50 i
Amendment No. J!, II, 57, fJ, Iff, !!8.128 I
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PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A l
SECTION DESCRIPTION PAGE NO 4.0 SURVEILLANCE REQUIREMENTS 4-1 j
4.1 INSTRUMENTATION AND CONTROL 4-1 4.1.1 Overpressure Protection Systems 4-1 Minimum Frequencies for Checks, Calibrations and Table 4.1.1 Testing of Reactor Protective System 4-3
. Table 4.1.2 Minimum Frequencies'for Checks, Calibrations and Testing of Engineered Safety Feature Instrumentation Controls 4-6 Table 4.1.3 Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls 4-10.
4.2 EQUIPMINT AND SAMPLING TESTS 4-13 Table 4.2.1 Minimum Frequencies for Sampling Tests 4-14 Table 4.2.2 Minimum Frequencies for Equipment Tests 4-15 Table 4.2.3 HEPA Filter and Charcoal Adsorber Systems 4-15c 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 PRIMARY COOLANT SYSTEM INTEGRITY TESTING 4-24 4.5 CONTAINMENT TESTS 4-25 4.5.1 Integrated Leakage Rate Tests 4-25 4.5.?
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 Valveo 4-32 /
4.5.7 De?eted 4-32a /
4.5.8 Deue Delamination Surveillance 4-32a /
4.6 SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEMS TESTS 4-39 4.6.1 Safety Injection System 4-39 4.6.2 Containment Spray System 4-39 4.6.3 Pumps 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 L
4.7.2 Station Batteries 4-42 4.7.3 Emergency Lighting 4-43 4.8 MAIN STEAM STOP VALVES 4-44 4.9
' AUXILIARY FEEDWATER SYSTEM 4 4.10 REACTIVITY ANOMALIES 4-46 4.11 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, it, 95,109,128
MISC'LLANEOUS DEFIN2TIONS E
1.4 Operable A system.or component is operable if it is capable of fulfilling its
' design functions.
Operating A system or component is operating.if it is performing its design functions.
Con, trol Rods A12 full-length shutdown and regulating rods.
Containment Integrity Containment integrity is defined to exist when all of the following are true:
a.
All nonautomatic containment isolation valves and blind flanges are closed (operable) except as noted in Table 3.6.1.
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b.
The equipment door is properly closed and sealed.
c.
At least one door in each personnel air lock is properly closed and sealed.
d.
All automatic containment isolation valves are operable (as
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demonstrated by satisfying isolation times specified in Table 3.6.1
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l and leakage criterion in Specification 4.5.2) or are locked closed.
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e.
The uncontrolled containment leakage satisfies Specification 4.5.1.
Dose Equivalent I-131 l
Dose Equivalent I-131 shall be that concentration of I-131 (uC/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, 1-132. I-133, I-134 and I-135 actually present. The thyroid dose conversion factors used for this
. calculation shall.be those listed in Table III of TID-14844,
" Calculation of Distance Factors for Power and Test Reactor Sites."
E - Average Disintegration Energy E shall be the average (weighted in proportion to the concentration of each radionuclides in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MEV) for isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95% of the total noniodine activity in the coolant.
1-4 Amendment No. 20, 43, 67, $5,128 l
i
-4 1.4.MISCEI.LANEOUS DEFINITIONS (Continued)
Safety Safety as'used in these' Technical Specifications refers to those safety _ issues related to the nuclear. process and, for example, does p
not encompass OSHA considerations.
l Reportable Event i
A reportable' event shall be any of'those conditions specified in Section 50.73 to 10 CFR Part 50.
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1-5 Amendment No. II, 128
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, 3.6 CON'TAINMENT SYSTEM i
Applicability Applies to the reactor containment building.
i Objective To assure the integrity of the reactor containment building.
Specifications I
3.6.1 Containment Inteority I
a.
Containment integrity as defined in Specification 1.4 shall
/
not be violated unless the reactor is in the cold shutdown condition.
b.
Containment integrity shall not be violated when the reactor vessel head is removed unless the boron concentration is greater then refueling concentration.
c.
Except for testing one rod at a time, positive reactivity changes shall not be made by control rod motion or boron dilution unless the containment integrity is intact.
ACTION:
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With one or more containment isolation valve (s) inoperable
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(including during performance of valve testing), maintain at
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least one isolation valve operable in each affected penetration
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that is open and either:
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a.
Restore the inoperable valve (s) to operable status within
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4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or
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b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use
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of at least one deactivated automatic valve secured in
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the isolation position, or
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c.
Isolate the affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use
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of at least one closed manual valve or blind flange; or
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d.
Be in at least hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and
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in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
/
BASIS The operability of the containment isolation valves ensures that
/
the containment atmosphere will be isolated from the outside
/
environment in the event of a release of radioactive material to
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the containment atmosphere or pressurization of the containment.
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3-40 Arrendment No.J28
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3.6. '
CONTAINMENT SYSTEM-- (Centinusd):
3.6.1 BASIS (Continued)
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i Containment isolation ensures th'at the' release'of' radioactive
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material to the environment will be consistent with the.
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' assumptions.used in Section 14 events of the Palisades FSAR.
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The above' Action requirements. provide time in which' trouble-
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shooting repairs and pressure testing of isolation valves
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3.6 C NTAINMENT SYSTEM (Continusd)
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3.6.2 The internal pressure shall not exceed 3 psig (except for containment leak rate tests).
3.6.3 Prior to the reactor going critical after a refueling outage, an administrative check will be made to confirm that all " locked-closed" manual containment isolation valves are closed and locked.
BASIS The primary coolant system conditions of cold shutdown assure that no steam will be formed and, hence, there would be no pressure buildup in the containment if~the primary coolant system ruptures. The shutdown margins are selected based on the type of activities that are being carried out.
The refueling boron concentration provides shutdown margin.which precludes criticality under any circumstances.
Regarding internal pressure limitations, the containment design pressure of 55 psig would not be exceeded if the internal press before a major loss-of-coolant accident were as much as 4 psig.y{y The containment integrity will be protected if the visual check of all " locked-closed" manual isolation _ valves to verify them closed is made prior to plant start-up after an extended outage where one or more valves could inadvertently be 2 eft open.
References (1) FSAR, Section 14.18, 3.6.4 Two independent containment hydrogen recombiners shall be operable when the reactor is at power or at hot standby. With one hydrogen recombiner system inoperable, restore the inoperable system to operable status within 30 days or be f.n at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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3-40f
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Amendment No. 81, 128
.6'.
CONTAINMENT' SYSTEM (Contd) 3.6.5 Containment Purge and Ventilation Systems a.. The containment purge and ventilation isolation valves CV 1805, CV 1806, CV 1807 CV 1808 and air room _ supply isolation valves CV 1813 and CV 1814 shall be electrically locked closed:whenever thr: reactor is in a HOT SHUTDOWN, HOT STANDBY, or POWER OPERATION condition.
b.
With one containment purge exhaust isolation valve or one air room supply isolation valve open, close the open valve within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUIDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
BASIS The containment purge and ventilation isolation velves are required to be closed in conditions above COLD SHUTDOWN, until it can be demonstrated that the valves meet the requirements of Standard Review Plan 6.2.4 and Branch Technical Position CSB 6-4.
To ensure that the valves are closed and that the seals have not degraded, a between the valves leak rate test will be performed.
Maintaining these valves closed during plant operations ensures that excessive quantities of radioactive materials will not be released via the containment purge or ventilation systems as
/
detailed in a & b above.
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The current method of maintaining Containment Building pressure
/
below one psig is by the removal of non-condensible gases from
/
the Containment Building through a clean waste receiver tank whose
/
rupture dise has been removed and then ultimately to the Plant
/
stack. This path is isolated by two automatic isolation valves
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prior to entry into the Plant stach.
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3-40g
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Amendment 90, 123 l-
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l 4. 5'
' CONTAINMENT TESTS (Contd)L 4.5;4-
' Surveillance for Prestressing System (Contd)
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f.
If any element of the prestressing system fails to meet the acceptance, criteria of 4.5.4e., the reporting provision of Specification 6.9.2 shall apply.
- 4. 5. 5 ~
End Anchorage Concrete Surveillance a.- A'VT-1 visual' examination shall be performed on the end anchorage. concrete surface at the surveillance tendon anchor points for signs of cracking, popouts, spalling, or corrosion.
Concrete cracks having widths greater than 0.010 shall be evaluated and documented.
b.
The end anchorage concrete surveillance inspection interval shall be the same as tendon surveillance interval.
c.
Acceptance criteria
- 1. Crack widths shall be measured by using optical comparators or wire feeler gauge. Movements shall be measured by using demountable mechanical extensometers.
- 2. Concrete anchorage arets are acceptable if no concrete cracks are wider than 0.010 inches and no signs of new or progressive deterioration since the previous inspection are found.
- 3. Concrete surface conditions exceeding those stated in 4.5.5c.2 above shall be evaluated for the effect on tendon and containment structural integrity. The results of evaluation shall be included in the final surveillance report.
4.5.6 Containment Isolation Valves
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a.
The isolation valves shall be demonstrated operable by
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performance of a cycling test and verification of isolation
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time for auto isolation valves prior to returning the valve
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to service after maintenance, repair or replacement work is
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performed on the valve or its associated actuator, control
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or power circuit.
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4-32 Amendment 14, 16, 109, 128
'-2'4.5, CONTAINMENT TESTS (Continu2d)
.4~5.6 Containment Isolation Valves (Continued) b.
Each isolation valve shall be demonstrated operable by verifying /
that on each containment isolation right channel or left channel /
test' signal, applicable isolation valves actuate to their
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required. position during cold shutdown or at least once per
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refueling cycle.
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c.
The isolation time of each power operated or automatic valve
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shall be determined to be within its limit as specified in
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Table-3.6.1 when tested in accordance with Section XI of the
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ASME Boiler and Pressure Vessel Code.
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4.5.7 Deleted
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4.5.8 Dome Delamination Surveillance If, as a result of a prestressing system inspection under Section 4.5.4, corrective retensioning of five percent (8) or more of the total number of dome tendons is necessary to restore their liftoff forces to within the limits of Specification 4.5.4, a dome delamination inspection shall be performed within 90 days following such corrective retensioning. The results of this inspection shall be reported to the NRC.
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4-32a
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Amendment 14, 16, 109, 128 i
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