ML20203H783
| ML20203H783 | |
| Person / Time | |
|---|---|
| Site: | Waterford  (NPF-38-A-149) |
| Issue date: | 02/17/1999 |
| From: | Chandu Patel NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20203H789 | List: |
| References | |
| NUDOCS 9902230121 | |
| Download: ML20203H783 (15) | |
Text
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UNITED STATES j
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001 ENTERGY OPERATIONS. INC.
DOCKET NO. 5Q-232 WATERFORD STEAM ELECTRIC STATION. UNIT 3 5
i AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.149 License No. NPF-38 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated June 29,1998, as supplemented by letter dated January 12,1999, 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 (i) that '.t.e 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 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.
9902230121 990217 PDR ADOCK 05000392 P
. 2.
Accordingly, the license is amended by changes to the Techr.ical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-38 is hereby amended to read as follows.
(2)
Technical Soecifications and Environrrental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 149, and the Environmental Protection Plan contained in Appendix B, 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 its date of issuance to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Chandu P. Patel, Project Manager Project Directorate IV-1 Division of Reactor Projects lil/lV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications Date of issuance:
February 17, 1999 I
-n v
ATTACHMENT TO L! CENSE AMENDMENT NO.149 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Replace the following pages of the Appendix ATechnical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to rnaintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 3-29 3/4 3-29 3/4 3-32 3/4 3-32 3/4 ~7-16 3/4 7-16 3/4 7-18 3/4 7-18 3/4 7-18a 3/4 7-18a 3/4 7-18b 3/4 7-18b 3/4 7-18c 3/4 7-18c 3/4 7-18d 3/4 7-18d B 3/4 7-4a B 3/4 7-4a B 3/4 7-4b B 3/4 7-4b B 3/4 7-4c B 3/4 7-4c i
l l
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TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION t
MINIMUM CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION 1.
AREA MONITORS 1
a.
Fuel Storage Pool Area Fuel Handing Buildmg ventitation System 4
Isolation 2
s 100 mR/h 10 - 10* mR/h 24 l
t 8
b.
Containment - Purge &
1/ train 1, 2, 3, 4 & **
40 mR/h or 20 - 5x10 mR/h 25 Exhaust isolation s 2x background whicheveris j
Higher 2.
PROCESS MONITORS l
a.
Containment Atmosphere 1)
Gaseous Actmty 4
4 RCS Leakaga Detecten 1
1, 2, 3, & 4 Not Applicable 10 -10 pCi/cc 23 l
2)
Particulate Actmty RCS Leakage Detecten 1
1, 2, 3, & 4 Not Applicable 10~" - 10 pCi/cc 23 4
b.
Control Room Intake Monitors 1/ intake ALL MODES & "*
s5.45x10 pCi/cc 10* - 10 pCi/cc 26 l'
4 4
c.
Steam Generator Blowdown Monitor 1
1, 2, 3, & 4 s10 pCi/cc 10* - 10 pCi/cc 28 4
4 1
i d.
Component Cooling Water 4
4 Monitors A&B 1/line ALL MODES s 10 pCi/cc 10-7-10 pCircc 28 e.
Component Cooling Water Monitor A/B 1
1, 2, 3, & 4 s 10 pCi/cc 10 10 pCi/cc 28 4
4
- With irradiated fuel in the storage pool.
[
"During CORE ALTERATIONS or movement of irradiated fuel within the containment.
l:!
"Dunng movement of irradiated fuel.
WATERFORD - UNIT 3 3/4 3-29 Amendment No. 55;9t;i44,
- 149,
TABLE 3.3-6 (Continued)
ACTION STATEMENTS A;T]DN 23 -
With the number of channels OPERABLE 1ess than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.5.1.
ACT10N 24 -
With the number of channels OPERABLE 1ess than required by the Minimum Channels CPERABLE requirew nt, comply with the ACTION requirements of Specification 3.9.12.
ACTION 25 -
With the number of channels OPERABLE 1ess than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.
1 ACTION 26 -
With the number of cha r als OPERABLE 1ess than required by the Minimum Channels OPERA.r. requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the control room emer system in the recirculation mode of operation. gency ventilation A:~30N 27 -
With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirement, either restore the inope-able Channel (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:
1.
Initiate the preplanned alternate method of monitoring the apprcpriate parameter (s), and 2.
If the monitor is not restored to OPERABLE status within 7 days after the failure, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schecule for restoring the system to CPERABLE status.
i A:~;;N 2E -
With the number of channels OPERABLE 1ess than required by the W nirue Channels OPERABLE requirements, operation of the plant may continue for up to 30 days provided grab samples are taken once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If the monitor is not restored to CPERABLE status within 30 days after the failure, continue sampling and prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
WATWORD - W17 3 3/4 3 31 Amendment No. 91
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TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES FOR WHICH l
CHANNEL-CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST IS REQUIRED l
1.
AREA MONITORS l
a.
Fuel Storage Pool Area f
i Fuel Handling Buildmg t
Ventilation System Isolation S
R Q
l
. s b.
Containment - Purge &
}
Exhaust isolation S
R Q
1, 2, 3, 4 & "
2.
PROCESS MONITORS a.
Containment Atmosphere l
1)
Gaseous Activity-RCS Leakage Detection S
R Q
1, 2, 3, & 4 '
2)
Partmulate Activity-RCS Leakage Detection S
R Q
1,2,3, & 4 i
b.
Control Room Intake Monitors S
R Q
ALL MODES & *"
ll l
c.
Steam Generator Blowdown S
R O
1, 2, 3, & 4 d.
Component Cooling Water
-l Monitors A&B S
R Q
ALL MODES t
e.
Component Coohng Water i
i Monitor NB S
R O
1, 2, 3, & 4
- With irradiated fuel in the storage pool.
"During CORE ALTERATIONS or movement of irradiated fuel within the containment.
t
- "Dunng movement of irradiated fuel.
L WATERFORD - UNIT 3 3/4 3-32 No. 9h96,
PLANT SYSTEMS 3/4.7.6.1 CONTROL ROOM EMERGENCY AIR FILTRATION SYSTEM LIMITING CONDITION FOR OPERATION
,3.7.6.1 Both control room emergency air filtration trains (S-8) shall be OPERABLE.
APPLICABILITY *: MODES 1,2,3, and 4.
l ACTION:
- a. -
With one control room emergency air filtration train inoperable, either restore the inoperable train to OPERABLE status within 7 days 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 />.
b.
With both control room emergency air filtration trains inopera'ble, restore one train to OPERABLE status 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 />.
SURVEILLANCE REQUIREMENTS 4.7.6.1 Each control room air filtration train (S-8) shall be demonstrated OPERABLE:
a.
At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 continuous hours with the heaters on.
b.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating witn the system by:
1.
Verifying that the filtration train satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5.a, C.5.c, and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 4225 cfm *105 2.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.
'During movement of irradiated fuel assemblies, TS 3.7.6.2 is also applicable.
l WATERFORD - UNIT 3 3/4 7-16 Amendment No.445349
l PLANT SYSTEMS
(
3/4.7.6.2 CONTROL ROOM EMERGENCY AIR FILTRATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.6.2 Two control room emergency air filtration trains (S4) shall be i
. APPLICABILITY: MODES 5,6, and during movement of irradiated fuel assemblies.
l ACTION.
l a.
.With one control room emergency air filtration system inoperable, l
restore the inoperable system to OPERABLE status within 7 days or initiate and maintain operation of the remaining OPERABLE control room emergency air filtration system in the recirculation mode.
b.
With both control room emergency air filtration systems inoperable, or with the OPERABLE control room emergency air filtration system, required to be in the recirculation mode by ACTION a, not capable of being powered by an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS and movement of irradiated fuel l
assemblies.
l l
l SURVEILLANCE REQUIREMENTS 4.7.6.2 The control room emergency air filtration trains (S-8) shall be j
demonstrated OPERABLE per the applicable Surveillance Requirements of 4.7.6.1.
l l
l 4
WATERFORD - UNIT 3 '
3/4 7-18 Amendment No. 4+5,149, l
Pl. ANT SYSTEMS j
3/4.7.6.*J CONTROL ROOM AIR TEMPERATURE LIMITING CONDITION FOR OPERATION 3.7.6.3 Two independent control room air conditioning units shall be OPERABLE.
a i
AEPLICABILITY': MODES 1,2,3, and 4.
l
=
ACTION:
i a.
With one control room air conditioning unit inoperable, restore the inoperable unit to OPERABLE status within 7 days or be in HOT STANDBY i
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 i i
30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
i l
b.
With two control room air conditioning units inoperable, retum one unit to an OPERABLE status 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 HOT STANDBY within l
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 />.
3
]
SURVEILLANCE REQUIREMENTS '
4.7.6.3 Each control room air conditioning unit shall be demonstrated j
OPERABLE:
i a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the operating control room air conditioning unit is maintaining average control room air temperature less than or equal to 80'F.
i
- b.
At least quarterly, if not performed within the last quarter, by
}
verifying that each control room air conditioning unit starts and j
operates for at least 15 minutes.
i j
i i
- During movement of irradiated fuel assemblies, TS 3.7.6.4 is also applicable.
WATERFORD - UNIT 3 3/4 718a Amendment No. 445,149
.~
PLANT SYSTEMS
~
3/4.7.6.4 CONTROL ROOM AIR TEMPERATURE LIMITING CONDITION FOR OPERATION 3.7.6.4 Two independent control room air conditioning units shall be OPERABLE.
9 l
APPLICABILITY: MODES 5,6, and during movement of irradiated fuel assemblies.
l ACTION:
a.
With one control room air conditioning unit inoperable, restore the inoperable system to OPERABLE etatus within 7 days or initiate and maintain operation of the remainirig OPERABLE control room air conditioning unit.
l b.
With both control room air conditioning units inoperable, or with the OPERABLE control room air conditioning unit, required to be in i
operation by ACTION a, not capable of being powered by an OPERABLE emergency power source, suspend all operations involving CORE j
ALTERATIONS and movement of irradiated fuel assemblies.
l SURVEILLANCE REQUIREMENTE, j
4.7.6.4 The control room air conditioning units shall be demonstrated i
OPERABLE per the Surveillance Requirements of 4.7.6.3.
l 1
1 i
i 1
WATERFORD - UNIT 3 3/4 7-18b Amendment No. 4+5)49, g
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7
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PLANT SYSTEMS 3/4.7.6.5 CONTROL ROOM ISOLATION AND PRESSURIZATION 1.lMITING CONDITION FOR OPERATION 3.7.6.5 The control room envelope isolation and pressurization boundaries shall be OPERABLE.
APPLICABILITY: All MODES and during movement of irradiated fuel assemblies.
l ACTION:
a.
With either control room envelope isolation valve in a normal outside air flow path inoperable, maintain at least one isolation valve in the flowpath OPERABLE, and either restore the inoperable valve to OPERABLE status with 7 days or isolate the affected flow path within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With any Control Room Emergency Filter Outside Air intake valve (s) inoperable, maintain at least one of the series isolation valves in a flowpath OPERABLE, and either restore the inoperable valve (s) to OPERABLE status within 7 days or isolate the affected flow path within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With more than one Control Room Emergency Filter Outside Air intake flow path inoperable, maintain at least one flow path per intake operable and restore an additional flow path to operable status within 7 days or, be in 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 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 />.
d.
With the control room envelope inoperable as a result of causes other than those addressed by ACTION (a), (b), or (c) above:
1.
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the control room envelope is inoperable, verify that the Emergency Breathing Airbanks pressure is greater than or equal to 1800 psig.
~
2.
MODES 1-4:
a.
If the cause of control room envelope inoperability is due to a known breach in the envelope of less than or equal to one square foot total area or the breach is associated with a permanent sealing mechanism (e.g., blocking open or removing a docr) then operation may continue for up to 7 days after the control room envelope is declared inoperable. Otherwise, be in 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 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 />.
WATERFORD - UNIT 3 3/4 7-18e Amendment No. +t5,149
~~
.. _. _. _ _ _..... _ _ _ _. _ _ ~. - - -
PLANT SYSTEMS LIMITING CONDITION FOR OPERATION
/LCI1ON: (Continued) b.
If the cause of control room envelope inoperability is unknown identify the cause within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. If the cause of the failure is due to a breach within the allowable limits of ACTION d.2.a then operation may continue for up to 7 days after the control room envelope is declared i
inoperable. Otherwise, be in 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 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 />.
c.
Should a toxic gas event occur, take immediate steps to restore control room envelope integrity.
3.
MODES 5, 6, and during movement of irradiated fuel assemblies:
l a.
Suspend all operations invoMng CORE ALTERATIONS and movement of irradiated fuel assemblies, and if a toxic gas event occurs, take immediate steps to restore control room envelope integrity.
SURVEll. LANCE REQUIREMENTS 4.7.6.5 The control room envelope isolation and pressurization boundaries j
shall be demonstrated OPERABLE at least once per 18 months by:
a.
Verifying that the control room envelope can be maintained at a
)
positive pressure of greater than or equal to 1/8 inch water gauge relative to the outside atmosphere with a make-up air flowrate less than or equal to 200 cfm during system operation.
b.
Verifying that on a toxic gas detection test signal, the system automatically switches to the isolation mode of operation, Verifyin~ that on a safety injection actuation test signal or a high c.
g radiation test signal, normal outside air flow paths isolate.
i 4'
WATERFORD - UNIT 3 3/4 7-18d Amendment No. 445,149
~
l l
PLANT SYSTEMS l
BASES l
3/4.7.5 FLOOD PROTECTION l
The limitation on flood protection ensures that facility protective actions will be taken in the event of flood conditions. The limit of elevation 27.0 ft Mean Sea Levelis based on the maximum elevation at which the levee provides protection, the nuclear plant island structure provides protection to safety-related equipment up to elevation +30 ft Mean Sea Level.
3/4.7.6.1 and 3/4.7.6.2 CONTROL ROOM EMERGENCY AIR FILTRATION SYSTEM During an emergency, both S-8 units are started to provide filtration and adsorption of l
outside air and control room envelope recirculated air (reference: FSAR 6.4.3.3). Dosages received after a full power design basis LOCA were calculated to be orders of magnitude higher than other accidents involving radiation releases to the environment (reference: FSAR Tables 15.6 18,15.7 2,15.7-4,15.7-5,15.7-7).
l The OPERABILITY of this system and control room design provisions are based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criterion 19 of Appendix A,10 CFR Part 50.
l The ACTION to suspend all operations involving movement of irradiated fuel assemblies shall not preclude completion of movement to a safe conservative position.
i Operation of the system with the heaters on for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> continuous over a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.
Obtaining and analyzing charcoal samples after 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of adsorber operation (since the last sample and analysis) ensures that the adsorber maintains the efficiency assumed in the safety analysis and is consistent with Regulatory Guide 1.52.
3/4.7.6.3 and 3/4.7.6.4 CONTROL ROOM AIR TEMPERATURE l
l l
Maintaining the control room air temperature less than or equal to 80*F ensures that (1) l the ambient air temperature does not exceed the allowable air temperature for continuous duty l
rating for the equipment and instrumentation in the control room, and (2) the control room will remain habitable for operations personnel during plant operation.
l The Air Conditioning System is designed to cool the outlet air to approximately 55'F.
Then, non safety-related near room heaters add enough heat to the air stream to keep the l
rooms between 70 and 75'F. Although 70 to 75'F is the normal control band, it would be too l
restrictive as an LCO. Control Room equipment was specified for a more general temperature
~
range to 45 to 120*F. A provision for the CPC microcomputers, which might be more sensitive to heat, is not required here. Since maximum outside air make-up flow in the normal ventilation mode comprises less than ten percent of the air flow from an AH-12 unit, outside air WATERFORD - UNIT 3 B 3/4 7-4a Amendment No.149 i
._Z
o PLANT SYSTEMS BASES CONTROL ROOM AIR TEMPERATURE (Continued) temperature has little affect on the AH-12s cooling coil heat load. Therefore, the ability of an AH-12 unit to maintain control room temperature in the normal mode gives adequate assurance of its capability for emergency situations.
The ACTION to suspend all operations invoMng movement of irradiated fuel assemblies shall not preclude completion of movement to a safe conservative position.
3/4.7.6.5 CONTROL ROOM ISOLATION AND PRESSURIZATION l
This specification provides the operability requirements for the control room envelope isolation and pressurization boundaries. The Limiting Condition for Operation (LCO) specifies specific ACTION STATEMENTS for inoperable components of the control room ventilation systems, separate from the S-8 and AH-12 units. The operability of the remaining parts of the system affect the ability of the control room ~ envelope to pressurize.
i ACTION STATEMENTS a and b focus on maintaining isolation characteristics. The l
l valves in the flow path referred to in ACTION a are HVC-102 & HVC-101. The Outside Air Intake (OAI) " series isolation valves" of ACTION b and c are as follows:
l NORTH OAl-HVC-202B & HVC-201 A HVC-202A & HVC-201B SOUTH OAl-HVC-204B & HVC-203A i
HVC-204A & HVC 203B ACTION STATEMENT c preserves the operator action (i.e., manually initiated filtered pressurization) that maintains the control room envelope at a positive pressure during a l
radiological emergency. As indicated above each OAl series isolation valve is powered by the i~
opposite train. With more than one OAl flow path inoperable a single failure (i.e., train A or B) could prohibit the ability to maintain the control envelope at a positive pressure. Therefore, in the specified condition, ACTION c requires an additional flow path to be returned to service within 7 days.
ACTION STATEMENT d.2.a is intended to address an intentional breach in the control room pressurization boundary as necessary to support maintenance or modification. A breach of this nature shall be limited in size and govemed under administrative controls. The size l
restrictions as stated in the ACTION are such that should a toxic event occur control room integrity can be immediately restored as described below. ACTION STATEMENT d.2.b is t
intended to restore pressurization ability as soon as possible for un;ntended breaches in the envelope. The 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to locate an unidentified breach is based on an evaluation that
_ considercd troubleshooting tasks that would be performed as necessary should the integrity of the Control Room Envelope pressure boundary fall into question. Estimated times associated l:
with each task were based on sound engineering Judgement. The ACTION statements also l
WATERFORD - UNIT 3 B 3/4 7-4b Amendment No. 446,149
=
o PLANT SYSTEMS BASES CONTROL ROOM (SOLATION AND PRESSURIZATION (Continued) recognize the MODE-independent nature of the toxic chemical threat and provides for operator protection in the event of a toxic chemical release concurrent with a breach in the control room envelope in addition, provisions have been added to the specification that, in the event of a toxic chemical event that threatens control room habitability while in the ACTION statements, "immediate steps" will be initiated to place the plant in a safe condition, in this context, the phrase "immediate steps
- is taken to mean that the operators should immedictely take reasonable action to restore a known breach in the envelope to an air-tight condition.
Amplifying instructions are provided in Waterford 3 Administrative procedures, which impose special controls for work that will breach the control room envelope.
The ACTION to suspend all operations involving movement of irradiated fuel assemblies shall not preclude completion of movement to a safe conservative position.
3/4.7.7 CONTROt t ED VENTILATION 4BD SYSTEM The OPERABILITY of the controlled ventilation area system ensures that radioactive materials leaking from the penetration area or the ECCS equipment within the pump room following a LOCA are filtered prior to reaching the environment. The operation of this system and the resultant effect on offsite dosage calculations was assumed in the safety analyses.
I 1
i i
I WATERFORD - UNIT 3 B 3/4 7-4c Amendment No. +t6,149 i
c j