ML18053A572

Proposed Tech Specs,Incorporating Containment Isolation Valve Spec to Allow for Manual Operation of Penetration 33 Isolation Valves at Power for Purpose of Sampling Safety Injection Tanks

ML18053A572
Person / Time
Site:	Palisades
Issue date:	09/15/1988
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18053A570	List: ML18053A568 ML18053A572 ML18053A587
References
NUDOCS 8809200079
Download: ML18053A572 (15)

Text

• ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 PROPOSED TECHNICAL SPECIFICATIONS PAGE CHANGES September 15, 1988 14 Pages OC0588-0022C-NL02-LI01~NL04 \~

PALISADES PLANT TECHNICAL SPECIFICATIONS 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 I 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 Figure 2-1 Reactor Core Safety Limits 2 Pump Operation 2-11 Figure 2-2 Reactor Core Safety Limits 3 Pump Operation 2-12 Figure 2-3 Reactor Core Safety Limits 4 Pump Operation 2-13 3.0 LIMITING CONDITIONS FOR OPERATION 3-1 3.0 APPLICABILITY 3-1 3.1 PRIMARY COOLANT SYSTEM 3-lb 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 3.1.8 Overpressure Protection Systems 3-25a 3.2 CHEMICAL AND VOLUME CONTROL SYSTEM 3-26 3.3 EMERGENCY CORE COOLING SYSTEM 3-29 3.4 CONTAINMENT COOLING 3-34 3.5 STEAM AND FEEDWATER SYSTEMS 3-38 3.6 CONTAINMENT SYSTEM 3-40 I Table 3.6.1 Containment Penetrations and Valves 3-40b I 3,7 ELECTRICAL SYSTEMS 3-41 3.8 REFUELING OPERATIONS 3-46 3.9 EFFLUENT RELEASE (DELETED) 3-50 i

Amendment No. 'l>t, '/J1, 'f,7, S$, f 0S '* .

OC0588-0022C-NL02-LI01-NL04

SECTION PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A DESCRIPTION PAGE NO 4.0 SURVEILLANCE REQUIREMENTS 4-1 4 .1 INSTRUMENTATION AND CONTROL 4-1

4. L 1 Overpressure Protection Systems 4-1 Table 4 .1.1 Minimum Frequencies for Checks, Calibrations and 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 EQUIPMENT 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 4.5.2 Local Leak Detection Tests 4-27 4.5.3 Recirculation Heat Removal Systems 4-28 4.5.4 Surveillance for Prestressing System 4-29 4.5.5 End Anchorage Concrete Surveillance 4-30 4.5.6 Containment Isolation Valves 4-31 I 4.5.7 Deleted 4-32 4.5.8 Dome 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 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 4-45 4.10 REACTIVITY ANOMALIES 4-46 4.11 -RADIOLOGICAL ENVIRONMENTAt 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. i7, ~S. ~i. ~7.

~S. SJ, l0S, OC0588-0022C-NL02-LI01-NL04

1.4 MISCELLANEOUS DEFINITIONS 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.

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 in Table 3.6.1. I

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 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 thyroid 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 Amendment No. $7, SJ~

OC0588-0022C-NL02-LI01-NL04

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.

1-5 Amendment No. $$,

OC0588-0022C-NL02-LI01-NL04

3.6

• CONTAINMENT SYSTEM Applicability Applies to the reactor containment building.

Objective To assure the integrity of the reactor containment building.

Specifications 3.6.1 Containment Integrity

a. Containment integrity as defined in Specification 1.4 shall I 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 boron concentration unless the containment integrity is intact. I ACTION_:

With one or more containment isolation valve(s) inoperable I (including during performance of valve testing), maintain at I least one isolation valve operable in each affected penetration I that is open and either: I

a. Restore 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 I of at least one deactivated automatic valve secured in_ I the isolation position, or I

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 I of at least one closed manual valve or blind flange; or I

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 I 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 />. I BASIS The operability of the containment isolation valves ensures that I the containment atmosphere will be isolated from the outside I environment in the event of a release of radioactive material to I the co~tainment atmosphere or pressurization of the containment. I 3-40 Amendment No.

OC0588-0022C-NL02-LI01-NL04

3.6 3.&.l CONTAINMENT SYSTEM BASIS (Continued)

(Continued)

Containment isolation ensures that the release of radioactive I material to the environment will be consistent with the I assumptions used in Section 14 events of the Palisades FSAR. I The above limiting conditions of operation provide time in which troubleshooting, repairs and pressure testing of isolation valves may occur.

3-40a Amendment No.

OC0588-0022C-NL02-LI01-NL04

TABLE 3.6.1 I CONTAINMENT PENETRATIONS AND VALVES I I

I SYSTEM NAME AND VALVE I P~ NUMBER .. ,SE~V_Il:;K ):.I~. SIZ_E . ... _Ip NIJ ... - - ..... REWJU<S 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 BOTTOM BLOWDOWN CV-0771 required closure .I (2") time = 25 seconds I I

I 6 S/G (E-50B) CV-0768 Auto isolation valve; I BOTTOM BLOWDOWN CV-0770 required closure I (2") time = 25 seconds I I

I I

11 CONDENSATE TO CV-0939 Auto isolation valve; I SHIELD COOLING CK-CD401 required closure I SURGE TANK time = 25 seconds I (1 1/2") I I

I 14 COMPONENT COOLING CV-0910 Auto isolation valve; I WATER IN (10") CK-CC0910 required closure I time = 25 seconds I I

I 15 COMPONENT COOLING CV-0911 Auto isolation valve; I WATER OUT (10 11 ) CV-0940 required closure I time = 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

3-40b*

Amendment No.

TSP0988-0001A-NL04

TABLE 3.6.1 *;' I CONTAINMENT PENETRATIONS AND VALVES I I

I SYSTEM NAME AND VALVE I

I'~.~~R. . . . . !)ERVIGE i.I~. SIZE . _IP NO . ~. I I

I Zl Hz MONITOR SV-Z415A Auto isolation valve; I (l/Z") SV-Z415B required closure I time = Z5 seconds I

- - . - --.. . - . -. - - . I I

ZlA Hz MONITOR SV-2413A Auto isolation valve; I (1/2") SV-2413B required closure I 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 Z6 NITROGEN TO CV-1358 Auto isolation valve; I CONTAINMENT CK-Nz400 required closure I (l") time = Z5 seconds I I

I 33 SAFETY INJECTION MV-ES3334 These valves are allowed I TANK .DRAIN (2 11 ) MV-ES3334A 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-Z009 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

I 38 CONDENSATE RETURN CV-1501 Auto isolation valve; I FROM STEAM HEATING CV-1502 required closure I UNITS (2") time = 25 seconds I

- . - . - ..... . .. - ..... . - ... - - . I 3-40c Amendment No.

TSP0988-0001A-NL04

TABLE 3.6.1 I CONTAINMENT PENETRATIONS AND VALVES I I

I SYSTEM NAME AND VALVE I

!?EN ~~R ... SERVI~E LI~ SIZ~.. .. IP. NO *-~- I I

I 39 CONTAINMENT HEATING CV-1503 Auto isolation valve; I SYSTEM (4") Blind flange in required closure I place during time = 25 seconds I power operation I I

I 40 PRI-COOLANT SYSTEM CV-1910 Auto isolation valve; I SAMPLE LINE (1/2") CV-1911 required closure I time = 25 seconds I I

I 40A H2 ~ONITOR SV-2414A Auto isolation valve; I (1/2,") SV-2414B required closure I time = 25 seconds I

... \ . . . - ... -. ... - .... I I

40B H2 MpNITOR SV-2412B Auto isolation valve; I (1/2!') SV-2412B required closure I time = 25 seconds I

.. .. J. .. . - - . . . . . . . ~ . - - -. . . . - . - - ..

I I

41 DEGASIFIER PUMP CV-1004 Auto isolation valve; I DISCHARGE (3") CK-CRW407 required closure I time = 25 seconds I

~ -. - .. . .

I I

42 DEMINERALIZED CV-0155 Auto isolation valve; I WATER TO QUENCH CK-V0155B required closure I TANK (2 11 ) time = 25 seconds I I

I 44 CONTROLLED BLEED-OFF CV-2083 Auto isolation valve; I FROM RCP'S CV-2099 required closure I (3/4") time = 25 seconds I I

I 46 CONTAINMENT VENT CV-1101 Auto isolation valve; I HEADER (4 11 ) CV-1102 required closure I time = 25 seconds I

.... - .. - . I 3-40d Amendment No.

TSP0988-0001A-NL04

TABLE 3.6.1 I CONTAINMENT PENETRATIONS AND VALVES I I

I SYSTEM NAME AND VALVE I

?EN. NmIB~!l. .. 1)E)lVI~E. J:..INE S_IZ~. . ID_ NO. .~fl. I I

I 47 PRIMARY SYSTEM CV-1002 Auto isolation valve; I DRAIN TANK PUMP CV-1007 required closure I SUCTION (4") time = 25 seconds 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 11 ) . time = 25 seconds I

- - . - ... - I I

55 S/G (E-50B) SURFACE CV-0738 . Auto isolation valve; I BLOWDOWN (2") required closure. I time = 25 seconds I

. . . - ...... . . - - . . . -. . . - . - - - - .. I I

67 CLEAN WASTE CV-1037 Auto isolation valve; I RECEIVER TANK PUMP CK-CRW408 required closure I RECIRC (3 11 ) 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") t-ime = 25 seconds I I

3-40e Amendment No.

TSP0988-0001A-NL04

3.6 3.6.2 CONTAINMENT SYSTEM (Continued)

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 pressyy, 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.

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 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.

OC0588-0022C-NL02-LI01-NL04

3.6 CONTAINMENT SYSTEM (Contd) 3.6.5 Containment Purge and Ventilation ~ystems

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 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 below one psig is by the removal of non-condensible gases from the Containment Building through a clean waste receiver tank whose rupture disc has been removed and then ultimately to the Plant stack. This path is isolated by two automatic isolation valves I prior to entry into the ¥!ant stack. /

3-40g Amendment St, 90, OC0588-0022C-NL02-LI01-NL04.

4.5 4.5.4 CONTAINMENT TESTS (Contd)

Surveillance for Prestressing System (Contd)

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 areas 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

a. The isolation valves shall be demonstrated operable by /

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<<, t~, t~~'

OC0588-0022C-NL02-LI01-NL04

,........~

4.5 4.5.6 CONTAINMENT TESTS (Continued)

Containment Isolation Valves (Continued)

b. Each isolation valve shall be demonstrated operable by ve~ifying I that on each containment isolation right channel or left channel I 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 or automatic valve I 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 4.5.7 Deleted 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.

4-32a Amendment l~, l~, 10~,

OC0588-0022C-NL02-LI01-NL04