ML20066J359
| ML20066J359 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/25/1991 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO) |
| Shared Package | |
| ML20066J361 | List: |
| References | |
| NPF-49-A-059 NUDOCS 9101310175 | |
| Download: ML20066J359 (15) | |
Text
_. _. _.._ _ _ _ ___ _._.__._._
[pn naap,#'g UNITED STATES I'
NUCLEAR REGULATORY COMMISSION s.e,
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W ASHINGTON, D. C. 20555 o,
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j, NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.'59-License No. NPF-49 1
1.
The Nuclear Regulatory Commission (the Commission) has found that:
4 The app (lication for amendment by Northeast Nuclear Energy Company, A.
et al.
the licensee) dated February 26, 1990, as supplemented April 30, December 6 and 19, 1990, 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, the provisions of the Act, and the rules and regulations of the Commission; 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 Comission's regulations; D.
The issuance of 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.
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I 2.
Accord.ingly, 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-49 is hereby amended to read as follows:
i (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 59 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.
This license amendment is effective as of the date of its issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Jo ' F. Stolz, Direc r
i ject Directorate I.4 l
ivision of Reactor-Projects '- I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 25, 1991 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 59 EACILT!Y OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following pages of the Appendix A Technical Specifications with the enclo:ed pages.
The revised pages are identified by amendment number and contein vertica' lines indicating the areas of change.
Remove Insert viii viii ix ix 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-4 3/4 6-4 3/4 6-5 3/4 6-5 3/4 6-6 3/4 6-6 3/4 6-7 3/4 6-7 3/4 6-8 3/4 6-8 B 3/4 6-1 B 3/4 6-1 B 3/4 6-2 B 3/4 6-2 l-
)
INDEX j
LIMITING CONDITIONS FOR OPEP.ATION AND SURVEILLANCE RE0VIREMENTS SECTION EM1 FIGURE 3.4-1 DOSE EQUIVALENT 1131 REACTOR COOLANT SPECIFIC i
ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE REACTOR COOLANT SPECIFIC ACTIVITY
- 1*Ci DOS E EQUIVAL ENT 1131............................./ gram 3/4 4 30 TABLE 4.4 4 REACTOR COOLANT SPECIFIC ACTIVITY SAMPLE AND PR0 GRAM......................................... ANALYSIS 4
3/4 4-31 i
3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Cool ant System....................
3/4 4-33 FIGURE 3.4-2 REACTOR COULANT SYSTEM HEATUP LIMITATIONS -
APPLICABLE UP TO 10 EFPY.................................
3/4 4 34 FIGURE 3.4-3 REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS -
APPLICABLE UP TO 10 EFPY.................................
3/4 4-35 TABLE 4.4-5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM -
WITHDRAWAL SCHEDULE.......................................
3/4 4-36 Pressurizer..............................................
3/4 4 37 Overpressure Protection Systems..........................
3/4 4-38 FIGURE 3.4-4a NOMINAL MAXIMUM ALLOWABLE ?0RV SETPOINT FOR THE COLD OVERPRESSURESYSTEM(FOURLOOPOPERATION)................
3/4 4 40 FIGURE 3.4-4b NOMINAL MAXIMUM ALLOWABLE PORV SETPOINT FOR THE COLD OVERPRESSURE SYSTEM (THREE LOOP OPERATION)............,... 3/4 4-41 i
3/4.4.10 STRUCTURAL INTEGRITY.....................................
3/4 4 42 3/4.4.11 REACTOR COOLANT SYSTEM VENTS.............................
3/4 4-43 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS.............................................
3/4 5 1 3/4.5.2 ECCS SUBSYSTEMS - T,yg GREATER THAN OR EQUAL TO 350....-
3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T,yg LESS THAN 350...................
3/4 5-7 3/4.5.4 REFUELING WATER STORAGE TANK............................,
3/4 5-9 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity....................................
3/.4 6-1 Containment Leakage.......................................
3/4 6-2 TABLE 3.6-1 ENCLOSURE BUILDING BYPASS LEAKAGE PATHS...............
3/4 6 4 Containment Air Locks....................................
3/4 6-5 Containment Pressure.....................................
3/4 6-7 MILLSTONE - UNIT 3 vili Amendment No. 59 L- - -. -
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4 J
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION.
Pf_QI t
Air Temperature...................................
3/4 6 9 Containment Structural Integri ty..................
3/4 6-10 Containment Ventilation System....................
3/4 6 11 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Quench Spray System....................
3/4 6-12 Recirculation Spray System.........................
3/4 6 13 Spray Additive System..............................
3/4 6-14 3/4.6.3 CONTAINMENT ISOLATION VALVES.......................
3/4 6-15 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Monitors..................................
3/4 6-35 Electric Hydrogen Recombiners......................
3/4 6-36 FIGURE 3.6 2 HYDROGEN RECOMBINER ACCEPTANCE CRITERIA FLOW VS.
CONTAINMENT PRESSURE...............................
3/46-36a 3/4.6.5 SUBATMOSPHERIC PRESSURE CONTROL SYSTEM Steam det Air Ejector..............................
3/4 6-37 3/4.6.6 SECONDARY CONTAINMENT Supplementary Leak Collection and Release System...
3/4 6-38 l
Enclosure Building Integrity......................--
3/4 6-40 Enclosure Building Structural Integrity............
3/4 6-41 3/4.7 PLANT SYSTEMS o
l 3/4.7.1 TURBINE CYCLE l
Safety Valves...........................................-
3/4 7-1 1
TABLE 3.7-1
. MAX!MUti ALLOWABLE POWER RANGE-NEUTRON FLUX HIGH
'SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING FOUR LOOP 0PERATION.........................
3/4 7-2 TABLE 3.7-2 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES THREE LOOP OPERAT10N..............................
3/4 7-2 Amendment N. 59 MILLSTONE - UNIT 3 ix
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l 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT l
CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY thall be maintained.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT IATEGRITY within I hour 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 />.
SURVEILLANCE RE0VIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
At least once per 31 days by verifying that all penetrations * -not a.
capable of being closed by OPERABLE containment automatic isolation valves or operator action during periods when containment isolation valves are opened under administrative control,** and required to be closed during accident conditions are closed by valves, ' blind flanges, or deactivated automatic valves secured in their positions, b.
By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3; and After each closing of each penetration subject to Type B testing, c.
except the containment air locks, if opened following a Type A or B test, by leak rate testing the seal with gas at a pressure not less than P 53.27 psia (38.57 psig), and verifying that when the measureh, leakage rate for these seals is added to the leakage rates determined pursuant to Specification 4.6.1.2d. for all other Type B and C penetrations, the combined' leakage-rate is less than 0.60 L '
a Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise-secured in the closed position.
These penetrations shall 1e verified closed during each COLD SHUTOOWN except that such verification need not be performed more often than once per 92 days.
The following manual valves may be opened on an intermittent basis under administrative control.
3FPW-V661, 3FPW 666, 3 SSP-V13, 3 SSP-V14, 3HCS-V2, 3HCS-V3, 3HCS-V9,- 3HCS V10,- 3HCS-V6,- 3HCS-V13, 3SAS V875, 3SAS-V50, 3CHS-V371, 3CCP-V886, 3CCP-V887, 3CVS-V13.
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MILLSTONE - UNIT 3 3/4 6-1 endm m No. 59
- i.
j CONTAINMENT SYSTEMS l
CONTAINMENT LEAKAGE l
LIMITING CONDITION FOR OPERATION 3.6.1.2 ' Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of less than or equal to L '
P,a O.65% by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 53.27 psia (38.57 psig);
b.
A combined leakage rate of less than 0.60 L for all penetrations and valves subject to Type B and C tests, when pressurized to P,;
and c.
A combined leakage rate of less than or equal to 0.042 L for all penetrations identified in Table 3.61 as Enclosure Buildihg bypass leakage paths when pressurized to P.
3 APPLICABILITY: H0 DES 1, 2, 3, and 4.
ACTION:
With the measured overall integrated containment leakage rate exceeding 0.75 L, or the measured combined leakage rate for all penetrations and valves s6bject to Type B and C tests exceeding 0.60 L, er the combined bypass leakage rate exceeding 0.042 L, restore the overill integrated leakage rete to less than 0.75 L, the combined leakage rate for all penetrations subject to Type B and C tests to less than 0.60 L,,
and the combined bypass leakage rate to less than 0.042 L prior to inc4asing the Reactor Coolant System a
temperature above 200'F.
SyfdllLLANCE RE0VIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at tlie following test schedule and shall be determined in conformance with the criteria specified in Appondix J of 10 CFR Part 50 using methods and provisions of ANSI t
l N45.4-1972 (Total Time Method) and/or ANSI /ANS 56.8-1981 (Mass Point Method):
i a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 10 month intervals during shutdown at a i
pressure not less than P, 53.27 psia (38.57 psig) during each 10-year service period. The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection; b.
If any periodic Type A test fails to meet 0.75 L the test schedule for subsequent Type A tests shall be reviewed ln,d approved by the Commission.
If two consecutive Type A tests fail to meet 0.75 L, a Type A test shall be performed at least every 18 months until two a
consecutive Type A tests meet 0.75 L at which time the above test schedule may be resumed; a
t N. 59 MILLSTONE - UNIT 3 3/4 6-2
.__._. _._ - _ ~.. _ _ _ _ _ _ _
L CONTAINMENT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued)
The accuracy of each Type A test shall be verified by a supplement.a1 c.
. test which:
l 1)
Confirms the accuracy of the test by verifying that the supple-mental test results, L, minus the sum of the Type A and the superimposedleak,L,isequaltoorlessthan0.25L,;
o 2)
Has a duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test; i
and i
3)
Requires that the rate at which gas.is injected into the containment or bled from the containment during the supplemental test is between 0.75 L and 1.25 L,.
a d.
Type B and C tests shall be conducted with gas at P, 53.27 psia (38.57 psig), at intervals no greater than 24 montds except for tests involving:
l 1)
Air locks e.
The combined bypass leakage rate shall be determined to be less than or equal to 0.042 L by applicable Type B and C tests at least once per 24 months exce$t for penetrations which are not indi'ridually testable; penetrations not individually testable shall br emined to have no detectable leakage when tested with soap bubb1;..
- lle the containment is pressurized to P,, 53.27 psig (38.57 psig,. during each Type A test; f.
Air locks shall be tested and demonstrated OPERABLE by the requirements of Specification 4.6.1.3; i
g.
Purge supply and exhaust isolation valves shall be demonstrated OPERABLE by the requirements of Specifications 4.6.3.2.c and 4.9.9.
h.
The provisions of Specification 4.0.2 are not applicable.
s Amendment No. 59 MILLSTONE - UNIT 3 3/4 6 3
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TABLE 3.6-1 i
i ENCLOSURE BUILDING BYPASS LEAKAGE PATHS i
PENETRATION DESCRIPTION RELEASE LOCATION I
14 N to Safety Injection Tanks Ground Release 2
15 Primary Water to Pressurizer Ground Release Relief Tanks 35 Vacuum Pump Suction Plant Vent 36 Vacuum Pump Suction Plant Vent 37 Air Ejector Suction Plant Vent i
38 Chilled Water Supply Plant Vent 45 Chilled Water Return Plant Vent 52 Service Air Turbine Building Roof Exhaust 54 Instrument Air Turbine Building Roof Exhaust 4
56 Fire Protection Ground Release 59 fuel Pool Purification Ground Release 60 Fuel Pool Purification Ground Release 70 Demineralized Water Ground Release I
72 Chilled Water Supply Plant Vent 85 Containment Purge Ground Release 86 Containment Purge Plant Vent 116 Chilled Water Return Plant-Vent I
l 124 Nitrogen to Containment Plant Vent i
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Amendment No. 59' MILLSTONE - UNIT 3 3/4 6-4
\\
CONTAINMfNT SYSTEMS CONTAINMENT AIR LOCKS i
LIMITING CONDITION FOR OPERATION i
3.6.1.3 'The containment air lock shall be OPERABLE with:
4 a.
Both doors closed except when the air lock is being used for normal transit entry and exit through the containment,. then at least one j
air lock door shall be closed, and 4
b.
An overall air lock leakage rate of less than or' equal to 0.05 L at P,,53.21 psia (3B.57psig).
a APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
4 a.
With one containment air lock door inoperable:
t 1.
Maintain at least the OPERABLE air lock door closed
- and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed, 2.
Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be = locked closed at least once per 31 days, 1
3.
Otherwise, 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 /> i
and in COLD SHUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, and 4.
The provisions of Specification 3.0.4 are not applicable, b.
With the containment air lock inoperable, except,as the result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 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 />.
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i
- Except during entry to repair an inoperable inner door, for a cumulative time not to exceed I hour per year.
^" " *
- MILLSTONE - UNIT 3 3/4 6-5.
CONTAINMFNT SYSTEMS SVRVEILLANCE RE0VIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:
a.
'1)
Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each closing, except when the air ~
lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying no detectable seal leakage by pressure decay when the volume between the door seals is pressurized to greater than or equal to P, 53.27 psia (38.57 psig), for at 3
least 15 minutes; 1
or 2)
Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each closing, except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying that the seal leakage is less than 0.01 L
as determined by precision flow measurements when measured f8r at least 30 seconds with the volume between the seals at a constant pressure of greater thar, or equal to P, 53.27 psia (38.57 psig);
a or 3)
Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each closing, except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by completing an overall air lock leakage test per 4.6.1.3.b.
b.
By conducting overall air lock leakage tests at not less than P,
53.27 psia (38.57 psig), and verifying the overall air lock leaka$e rate is within its limit:
1)
At least once per 6 months,* and 2)
Prior to establishing CONTAINMENT INTEGRITY when maintenance has been performed on the air lock that could affect the air lock sealing capability.**
At least once per 6 months by verifying that only one door in each c.
air lock can be opened at a time.
4 4
- The provisions of Specification 4.0.2 are not applicable.
- This represents an exemption to Appendix J, paragraph III.O.2.(b)(ii), of 10 CFR Part 50.
MILLSTONE - UNIT 3 3/4 6-6 Amendment No. 59
CONTAINMENT SYSTEMS CONTAINMENT PRESSURE LIMITING CONDITION FOR OPERATION
' Primary containment pres.ure shall be maintained greater than or 3.6.1.4 equal to 10.6 psia and less than ar equal to 14.0 psia.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With the containment pressure less than 10.6 psia or greater than 14.0 psia, restore the containment pressure to within the ?imits within I hour or be in 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 withi= the at following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVElllANCE RE0VIREMENTS 4.6.1.4 The primary containment pressure shall be determined to be within the limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
MILLSTONE - UNIT 3 3/4 6-7
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1 Amendment No. 59 l
MILLSTONE - UNIT 3 3/4 6 8
l 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.l CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses.
This restric-tion, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the dose guidelines of 10 CFR Part 100 during accident conditions and the control room operators dose to within the guidelines of GDC 19.
3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure, P,.
As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L, during performance of the periodic test to account for possible degradation of the containment leakage barriers between leakage tests.
The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix J of 10 CFR Part 50.
3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.
Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.
3/4.6.1.4 and 3/4.6.1.5 AIR PRESSURE and AIR TEMPERATURE The limitations on containment pressure and average air temperature ensure that:
(1) the containment structure is prevented from exceeding its design negative pressure of 8 psia, and (2) the containment peak pressure does not exceed the design pressure of 60 psia during LOCA conditions.
Measure-ments shall be made at all listed locations, whether by fixed or portable instruments, prior to determining the average air temperature.
The limits on the pressure and average air temperature are consistent' with the assumptions of the safety analysis.
The minimum total containment pressure of 10.6 psia is determined by summing the minimum permissible air partial pressure of l
8.9 psia and the maximum expected vapor pressure of 1.7 psia maximum permissible containment initial temperature of 120*F)(occurring at the Amendment No. 59 MILLSTONE - UNIT 3 B 3/4 6-1
. _ ~.__
i CONTAINMENT SYSTEMS BASES 3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the facility.
Structural integrity is required to ensure that the containment will withstand the maximum pressure of 60 psia in the event of-a LOCA.
A visual inspection in conjunction with the Type A leakage tests is sufficient to demonstrate this capability.
3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM The 42-inch containment purge supply and exhaust isolation valves are required to be locked closed during plant operation since these valves have not been demonstrated capable of closing during a LOCA or steam line break 4
accident. Maintaining these valves closed during plant operations ensures that excessive quantitles of radioactive materials will not be ralcased via the Containment Purge System.
To provide assurance that these~ containment valves i
cannot be inadvertently opened, the valves are locked closed in accordance with Standard Review Plan 6.2.4 which includes mechanical devices to seal or lock the valve closed, or prevents power from being supplied to the valve operator.
The Type C testing frequency required by 4.6.1.2d is acceptable, provided that the resilient seats of these valves are replaced every other refueling outage.
3/4.6.2 DEPRESSVRIZATION AND COOLING SYSTEMS 3/4.6.2.1 and 3/4.6.2.2 CONTAINMENT OVENCH SPRAY SYSTEM and RECIRCULATION l
SPRAY SYSTEM The OPERABILITY of the Containment Spray Systems ensures that containment depressurization and iodine removal will occur in the event of a LOCA.
The pressure reduction, iodine removal capabilities and resultant containment leakage are consistent with the assumptions used in the safety analyses.
3/4.6.2.3 SPRAY ADDITIVE SYSTEM The OPERABILITY of the Spray Additive System ensures that sufficient Na0H is added to the containment spray in the event of a LOCA.
The limits on Na0H volume and concentration ensure a pH value of between 7.0 and 7.35 for the solution recirculated within containment after a LOCA.
This pH band minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.
The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical charac-teristics.
Amendment No. 59 MILLSTONE UNIT 3 B 3/4 6-2 m.
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