ML18054A812

Corrected Proposed Tech Specs Re Containment Isolation Sys

ML18054A812
Person / Time
Site:	Palisades
Issue date:	06/23/1989
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18054A811	List: ML18054A810 ML18054A812
References
NUDOCS 8906280196
Download: ML18054A812 (15)

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*--------------ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 CORRECTED PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES 8906280196 890623 PDR ADOCK 05000255 P PNU TSP0689-0136-NL04

! I ' June 23, 1989 14 Pages \

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• PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS -APPENDIX A -----SECT-ION-

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PAGE __ _NQ _______ _ 1.0 1.1 1. 2 1.3 1.4 2.0 2.1 2.2 2.3 3.0 3.0 Table 2.3.1 3.1 3.1. 1 Figure 3-0 3.1. 2 Figure 3-1 Figure 3-2 _Figure 3-3 3.1. 3 3.1. 4 3.1. 5 3.1. 6 3.1. 7 3.1.8 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 Table 3.6.1 TSP0689-0136-NL04 DEFINITIONS REACTOR OPERATING CONDITIONS PROTECTIVE SYSTEMS INSTRUMENTATION SURVEILLANCE MISCELLANEOUS DEFINITIONS SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SAFETY LIMITS -REACTOR CORE SAFETY LIMITS -PRIMARY COOLANT SYSTEM PRESSURE LIMITING SAFETY SYSTEM SETTINGS -REACTOR PROTECTIVE SYSTEM Reactor Protective System Trip Setting Limits LIMITING CONDITIONS FOR OPERATION APPLICABILITY PRIMARY COOLANT SYSTEM Operable Components Reactor Inlet Temperature vs Operating Pressure Heatup and Cooldown*Rates Pressure -Temperature Limits for Heatup Pressure -Temperature Limits for Cooldown Pressure -Temperature Limits for Hydro Test Minimum Conditions for Criticality Maximum Primary Coolant Radioactivity

-Primary Coolant System Leakage Limits Maximum Primary Coolant Oxygen and Halogens Concentrations Primary and Secondary Safety Valves Overpressure Protection Systems CHEMICAL AND VOLUME CONTROL SYSTEM EMERGENCY CORE COOLING SYSTEM CONTAINMENT COOLING STEAM AND FEEDWATER SYSTEMS CONTAINMENT SYSTEI1 Containment Penetrations and Valves ELECTRICAL SYSTEMS -REFUELING OPERATIONS EFFLUENT RELEASE (DELETED) i 1-1 1-1 1-3 1-3 1-4 2-1 2-1 2-3 2-.4 2-5 3-1 3-1 3-lb 3-lb 3-3a 3-4 3-9 3-10 3-11 3-12 3-17 3-20 3-23 3-25 3-25a 3-26 3-29 3-34 3-38 3-40 3-40b 3-41 3-46 3-50 Amendment No. it, Jl, J7, SJ, t0S, t U, (II) (Date) I SECTION 4.0 4. 1 4.1. 1 Table 4.1.1 Table 4.1. 2 Table 4.1. 3 4.2 Table 4.2.1 Table 4.2.2 Table 4.2.3 . 4. 3 Table 4.3.1 Table 4.3.2 4.4 4.5 4.5.1 4.5.2 4.5.3 4.5.4 4.5.5 4.5.6 4.5.7 4. 5. 8 4.6 4.6.1 4.6.2 4.6.3 4.6.4 4.6.5 4.7 4.7.1 4.7.2 4.7.3 4.8 4.9 .. 4.10 4.11 Table 4.11-1 Table 4.11-2 TSP0689-0136-NL04

• PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS -APPENDIX A DESCRIPTION

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*-**----------------------------SURVEILLANCE REQUIREMENTS INSTRUMENTATION AND CONTROL Overpressure Protection Systems Minimum Frequencies for Checks, Calibrations and Testing of Reactor Protective System Minimum Frequencies for Checks, Calibrations and Testing of Engineered Safety Feature Instrumentation Controls Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls EQUIPMENT AND SAMPLING TESTS Minimum Frequencies for Sampling Tests Minimum Frequencies for Equipment Tests HEPA Filter and Charcoal Adsorber Systems SYSTEMS SURVEILLANCE Primary Coolant System Pressure Isolation Valves Miscellaneous Surveillance Items PRIMARY COOLANT SYSTEM INTEGRITY TESTING CONTAINMENT TESTS Integrated Leakage Rate Tests Local Leak Detection Tests Recirculation Heat Removal Systems Surveillance for Prestressing System End Anchorage Concrete Surveillance Containment Isolation Valves Deleted Dome Delamination Surveillance SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEMS TESTS Safety Injection System Containment Spray System Pumps Valves (Deleted)

Containment Air Cooling System EMERGENCY POWER SYSTEM PERIODIC TESTS Diesel Generators Station Batteries

• Emergency Lighting MAIN STEAM STOP VALVES AUXILIARY FEEDWATER SYSTEM REACTIVITY ANOMALIES RADIOLOGICAL ENVIRONMENTAL MONITORING Radiological Environmental Monitoring Program Reporting Levels for Radioactivity Concentrations in Environmental Samples iv PAGE NO 4-1 4-1 4-1 4-3 4-6 4-10. 4-13 4-14 4-15 4-15c 4-16 4-19 4-23 4-24 4-25 4-25 4-27 4-28a I 4-29 4-32 I 4-32 I 4-32a I 4-32a I 4-39 4-39 4-39 4-39 4-40 4-40 4-42 4-42 4-42 4-43 4-44 4-45 4-46 4..:.47 4-49 4-56 Amendment No. 17, u, 10s, un (Date)

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• 1.4 MISCELLANEOUS DEFINITIONS Operable.

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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.

Control Rods All 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 iri Table 3.6.1. b. The equipment door is properly closed and sealed. c. At least one in each personnel air lock is properly closed and sealed. -----------

I d. All automatic containment-isolation valves are operable (as I demonstrated by satisfying isolation times specified in Table 3.6.1 I and leakage criterion in Specification 4.5.2) or are locked closed. I e. The_ uncontrolled containment leakage satisfies Specification 4.5.1. ,-Dose Equivalent I-131 Dose Equivalent I-131 shall be that concentration of I-131 (uC/gram) which alone would produce the same-thyrqid dose as the quantity and isotopic mixture of I-131, I-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 radionuclide 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 TSP0689-0136-NL04 Amendment No. $7, S$, (#) (Date)

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-1.4 MISCELLANEOUS DEFINITIONS (Continued)

Safety \ Safety as used in these Technical Specifications refers to those safety issues related to the nuclear process and, for example, does not encompass OSHA considerations.

Reportable Event A reportable event shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50. (Note -no changes in text, included for continuity only) 1-5 Amendment No. 85 TSP0689-0136-NL04

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't 3.6 3.6.1 *

• CONTAINMENT SYSTEM Applicability

--App-li-es-to-the-reactor-cont-ai-nment-bui-ld-ing.-

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_ Objective To assure the integrity of the reactor containment building.

Specifications Containment Integrity

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 than 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 to less than cold shutdown-b_oron concentration unless the containment integrity is intact. ACTION: With one or more containment isolation valve(s) inoperable (including during performance of valve testing), maintain at -least one isolation valve operable in each affected penetration that is open and either: I I I l I I I a. Restor& the inoperable valve(s) to operable status within I 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or I 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 of at least one deactivated automatic valve secured in the isolation position, or 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 of at least one closed manual valve or blind flange; or 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 ill 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 the containment atmosphere or pressurization of the containment.

3-40 Amendment No. (#) (Date) I I I I I I I I I I I TSP0689-0136-NL04

• 3.6 CONTAINMENT SYSTEM (Continued)

3. 6 .1 BASIS. (Continued) . -------------

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Containment isolation ensures that the release of radioactive

/ material to the environment will be consistent with the / assumptions used in Section 14 events of the Palisades FSAR. / The above Action requirements provide time in which shooting, repairs and pressure testing of isolation valves may occur. 3-40a TSP0689-0136-NL04 Amendment No. (II) (Date) I I I -------

I -* TABLE 3.6.1 I CONTAINMENT PENETRATIONS AND VALVES I I I SYSTEM NAME AND . VALVE I PEN NUMBER SERVlCE LINE SIZE ID NO REMARKS I I I lA PURGE AIR EXHAUST CV-1805 Auto isolation valve; I (8") CV-1806 required closure I time = 25 seconds I I I lC PURGE AIR EXHAUST CV-1807 Auto isolation valve; I * (8") CV-1808 required closure I time = 25 seconds I I I 5 S/G (E-50A) CV-0767 Auto isolation valve; I BCYI'TOM BLOWDOWN CV-0771 required closure I (2") time = 25 seconds I I I 6 S/G (E-50B) CV-0768 Auto isolation valve; I BCYI'TOM.BLOWDOWN CV-0770 required closure I (2") time a 25 seconds I I I I i I I 11 CONDENSATE TO CV-0939 Auto isolation valve; I I SHIELD.COOLING CK-CD401 required closure ! I I SURGE TANK time a 25 seconds I I (1 1/2 11) I I I ., I COMPONENT COOLING I 14 CV-0910 Auto isolation valve; I

• WATER IN (10") CK-CC0910 required closure I time = 25 seconds I I COMPONENT COOLING I 15 CV-0911 Auto isolation valve; I WATER OUT (10 11) CV-0940 required closure I time a *25 seconds I I I 16 S/G (E-50A) CV-0739 Auto isolation valve; I SURFACE BLOWDOWN required closure I (2") time = 25 seconds I I I I I 3-40b I I I / Amendment No, (/fa) / (Date) TSP0689-0136-NL04 TABLE 3,6.1 I CONTAINMENT PENETRATIONS AND VALVES I I SYSTEM NAME AND VALVE I I PEN NUMBER SERVICE LINE SIZE ID NO REMARKS I I i I I 21 H 2 MONITOR SV-2415A Auto isolation valve; /' I (1/2 11) i SV-2415B required closure I time = 25 seconds I I I I I 21A H 2 MONITOR SV-2413A Auto isolation valve; I (1/2 11) SV-2413B required closure I e* time = 25 seconds I I I 25 CLEAN WASTE CV-1064 Auto isolation valve; I RECEIVER TANK CV-1065 required closure I VENT TO STACK time = 25 seconds I (2") I I I 26 NITROGEN TO CV-1358 Auto isolation valve; I CONTAINMENT CK-N 2 400 required closure I (l") time = 25 seconds I I I 33 SAFETY INJECTION MV-ES3234 These valves are allowed I TANK DRAIN (2") MV-ES3234A to be open for testing/sampling I no more than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per sample I I I 36 LETDOWN TO CV-2009 Auto isolation valve; I PURIFICATION required closure I ION EXCHANGER (2") time = 25 seconds I

• I I 37 PRIMARY SYSTEM CV-1001 Auto isolation valve; I DRAIN TANK PUMP CK-CRW403 required closure I RECIRC (1 1/2") time = 25 seconds I I CONDENSATE RETURN I 38 CV-1501 Auto isolation valve; I FROM STEAM HEATING CV-1502 required closure I UNITS (2") time = 25 seconds I I I I I 3-40c I Amendment No. (ffa) (Date) ! TSP0689-0136-NL04 TABLE I CONTAINMENT PENETRATIONS AND VALVES I I I SYSTEM NAME AND VALVE I PEN NUMBER SERVICE LINE SIZE ID NO REMARKS I I I I I 39 CONTAINMENT HEATING CV-1503 Auto isolation valve; SYSTEM (4") Blind flange in required closure place* during time 0 25 seconds I power operation I I I

• I I I 40 PRI-COOLANT SYSTEM CV-1910 Auto isolation valve; SAMPLE LINE (1/2") CV-1911 required closure time 0 25 seconds I I I I I 40A H 2 MONiTOR SV-2414A Auto isolation valve; (1/2) SV-2414B required closure time a 25 seconds I I I I I 40B H 2 MONITOR . SV-2412B Auto isolation valve; (1/2") SV-2412B required closure time = 25 seconds I I I I 41 DEGASIFIER PUMP CV-1004 Auto isolation valve; DISCHARGE (3 11) CK-CRW407 required closure time= 25.seconds I I I I I

• I I 42 DEMINERALIZED CV-0155 Auto isolation v.alve; WATER TO QUENCH CK-V0155B required closure TANK (2 11) time = 25 seconds I 44 CONTROLLED BLEED-OFF CV-2083 Auto isolation valve; I I I FROM RCP'S CV-2099 required closure (3/4") time a 25 seconds I I I I. ' /. 46 CONTAINMENT VENT cv-1101 Auto isolation valve; HEADER (4"). CV-1102 required closure I time 0 25 seconds I I I I I I I I 3-40d Amendment No. un I (Date) I I I I I TSP0689-0136-NL04 I

TABLE 3.6.1 I CONTAINMENT PENETRATIONS AND VALVES I I I SYSTEM NAME AND VALVE I PEN NUMBER SERVICE LINE SIZE ID NO REMARKS I I I 47 PRIMARY SYSTEM CV-1002 Auto isolation valve; I DRAIN TANK PUMP CV-1007 required closure *1 I SUCTION (4") time = 25 seconds I I I I 49 CLEAN WASTE CV-1038 Auto isolation valve; I RECEIVER TANK CV-1036 required closure I ., CIRCULATION PUMP time = 25 seconds I SUCTION (3") I I I 52 CONTAINMENT SUMP CV-1103 Auto isolation valve; I DRAIN TO DIRTY WASTE CV-1104 required closure I TANK (4") time = 25 seconds I I I 55 S/G (E-50B) SURFACE CV-0738 Auto isolation valve; I BLOWDQWN.(2")

required closure I time = 25 seconds ,. I ' I CLEAN WASTE I 67 CV-1037 Auto isolation valve; I *RECEIVER TANK PUMP CK-CRW408 required cl9sure I RECIRC (3") time = 25 seconds I I I 68 AIR SUPPLY TO CV-1813 Auto isolation valve; I AIR ROOM (12") CV-1814 required closure I time = 25 seconds I

• I I 69 CLEAN WASTE CV-1045 Auto isolation valve; I RECEIVER TANK PUMP CV-1044 required closure I SUCTION (4") time .. 25 seconds I I I I I I I I I 3-40e I Amendment No. un ! (Date) I TSP0689-0136-NL04

• * 'f 3.6 CONTAINMENT SYSTEM (Continued) shall not exceed 3 psig (except for containment leak rate tests) . -------------------------------------

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_ 3.6.3 3.6.4 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 pressyI1 before a major loss-of-coolant accident were as much as 4 psig. 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 left open. References (1) FSAR, Section 14.18. 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 in 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 />. 3-40f Amendment No. Sl, (#) (Date) TSP0689-0136-NL04 I

-* 3.6 --------3.6.5 . *

• CONTAINMENT SYSTEM (Contd) ---------Containment

--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 c_losed whenever the 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 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 containment purge and ventilation isolation valves 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 I detailed in a & b above. I The current method of maintaining Containment Building pressure I below one psig is by the removal of non-condensible gases from I the Containment Building through a clean waste receiver tank whose

• I rupture disc has been removed and then ultimately to the Plant I stac_k. This path is isolated by two automatic isolation valves I prior to entry into the Plant stack. I 3-40g I Amendment (#) (Date) TSP0689-0136-NL04

• 4.5 CONTAINMENT TESTS (Contd) ----4-;5-;-4----Sul'-ye-ilJ.ance -for __

System (Contd) 4.5.5 4.5.6 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. 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 areas are acceptable if no .concrete cracks 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. Containment Isolation Valves ----

I a. The isolation valves shall be demonstrated operable by I performance of a cycling test and verification of isolation I time for auto isolation valves prior to returning the valve I to service after maintenance, repair or replacement work is_ I performed on the.valve or its associated actuator, control I or power circuit. I 4-32 Amendment t<<,

(#) (Date) TSP0689-0136-NL04

,;i 4.5 (Continued)

• 4.5.6 Containment Isolation Valves (Continued)

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• Each--is-olation--va1ve--sn.n1-1rn--demonstrated -operable

__ by _yerif.yj_ng

/ 4.5.7 4.5.8 that on each containment isolation right cha11.nel or left channel --*T*------

test signal, applicable isolation valves actuate to their I required position during cold shutdown or at least once per I refueling cycle. I c. The isolation time of each power operated automatic valve / shall be determined to be within its limit as specified in I Table 3.6.1 when tested in accordance with Section XI of the I ASME Boiler and Pressure Vessel Code. I Deleted 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 delaminatiort inspection shall be performed within 90 days following such corrective retensioning.

The results of this shall_ be reported to the NRC.

• 4-32a Amendment 14, 109, (#) (Date) I I TSP0689-0136-NL04