B14462, Proposed Tech Specs 3.4.4 & 3.4.9.3 Addressing Issues in GL-90-06
| ML20044F546 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 05/19/1993 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20044F473 | List: |
| References | |
| REF-GTECI-070, REF-GTECI-094, REF-GTECI-NI, TASK-070, TASK-094, TASK-70, TASK-94, TASK-OR B14462, GL-90-06, GL-90-6, NUDOCS 9305280239 | |
| Download: ML20044F546 (15) | |
Text
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i Docket No. 50-213 B14462 t
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Haddam Neck Plant Proposed Revision to Technical Specifications Marked Up Pages of Technical Specifications i
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May 1993
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APR 2 61990
' REACTOR COOLANT SVSTEM 3/4.4.4 RELIEF VALVES tIMITING CONDITION FOR OPERATION 3.4.4 VM power-operated relief valves (PORVs) and their associated block valves shall be OPERABLE. The Setpoint for the PORVs and their block valves shall be Feater than or equal to 2325 psig and less than or equal to 2350 psig. The emergency control air supply shall have a minimum pressure of 118 psig.
% c_mam cu sw. Maom/ cvereb APPLICABILITY: MODES 1, 2, and 3.
ACTION:
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a.
With one or'*ere ORV(s) inoperable, ecause of excessive seat le:hage, within I hour either restore the PORV(s) to OPERABL status or close/ verify closed the associated block valve (s ;
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 /> and in SHUTDOWN within the following ours.
b.
With one PORV inoperableTdoe--to-causes-etheMhan-excessive-seat
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- :urc, within 1 h "orcMwat hour either restore the PORV to OPERABLE status or close/ verify os a e % u.w, closed the associated block valve and remove power from the block cm r um valve; restore the PORV to OPERABLE status within the fo110 wing.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 in Q HUTDOWNwithinthefollowing.3gours.
c.
With both PORVs inoperable-due to cau e: Other th:r : = ::i n :::t le ce cr_'re =r=cy = trol :ir cupply pr=ure, within 1
@ crer cs. [chour either restore *c;;h ;f the PORVX to OPERABLE status or dose / verify closed *thcir ;;sociated block valves and remove power from the block valves and be in HOT STANDBY within the next 6
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. hours and SHUTDOWN within the following ours.
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With the emergency control air supply pressure for the PORVs less than 118 psig restore the emergency control air supply to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 in SHUTDOWN within the following hours.
SURVEILLANCE RE0VIREMENTS 1
4.4.4.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE at least once per 18 months by:
a.
Performance of a CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST, and b.
Operating the valve through one complete cycle of full trave.
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HADDAM NECK 3/4 4-20 Amendment No. 125 O/7 /
a.
INSERT A c.
With one or both block valves inoperable and not capable of _ being manually cycled within I hour restore the block valve (s) to OPERABLE status or place its associated PORV(s) controls in the "close" position.
Restore at least one block valve to OPERABLE status within the next hour if both block valves are inoperable; restore any remaining inoperable block valve to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; otherwise, be in at least IlOT 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 IlOT SIIUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
f.
With one or more block valves INOPERABLE and capable of being manually cycled, within one hour close the block valve and place its associated PORV in the "close" position i
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APR 2 61990 t
. REACTOR COOLANT SYSTEM S1)RVEILLANCE REOUIREMENTS 4.4.4.2 Each PORV block valve shall be demonstrated OPERABLE at least once per 18 months by performance of an ANALOG CHANNEL OPERATIONAL TEST.
4.4.4.3 Each PORY block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed with power removed in order to meet.the requirements of ACTION b. or c. in Specification 3.4.4.
4.4.4.4 The control air supply for the PORVs shall be demonstrated OPERABLE at least once per 18 months by verifying that the control air supply does not drop more than 0.3 psi in one hour when isolated from Containment Air Supply System.
4.4.4.5 The air supply for the PORVs shall be verified by local pressure indication once every 92 days.
4.4.4.6 The emergency air :nd p :::. supply for the PORVs nd bic:k V ht:
shall be demonstrated OPERABLE at least once per 18 months be
% )(anually transferring pe&r:cr :nd airLand control p :::f. from the 199-f normal to the emergency per:r :nd air supp (es., andW 4 JIperating the valves through a complete cycle of full travel.
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HADDAM NECK 3/4 4-21 Amendment No. 125 l
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APR 2 61990 REACTOR COOLANT SYSTEM LOW TEMPERATURE OVERPRESSURE PROTECTION SYSTEMS "C'
LIMITING CONDITION FOR OPERATION 3.4.9.3 At least one of the following Low Temperature Overpressure Protection (LTOP) Systems shall be OPERABLE:
a.
Two LTOP spring-loaded relief valves (SLRV) with a lift setting of 380 (i3%) psig with their respective motor-operated isolation valves in the open position, or b.
The Reactor Coolant System (RCS) depressurized with an RCS vent of greater than or equal to 7 square inches (3 inches nominal inside diameter).
APPLICABILITY:
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MODE 4 when the temperature of any RCS cold leg of an unisolated loop is less than or equal to 315'F, excep during the performance of hydrostatic or leak testing.
MODE 5 and MODE 6 with the r::cter ;;;;cl h :d cr..
The ebeve-overpressure protection system shall be placed in service prior to placing the RHR system into service and sh 11 remain in service unless the requirements of Specification 3.4.9.3.b are sa sfied.
ACTION:
b a.
With one LTOP SLRV inoperable inoperable LTOP SLRV to t
OPERABLE status within 7 days, or4aepressurize angvent the RCS through at least a 7 square inch vent within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
u so cel shsActed umb we he..Ay C.ctb SfUrDLp go,%' L~:y hears e a C g.
With both LTOP SLRVs inoperable, depressurize and vent the RCS through at least a 7 square inch vent within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
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In the event either the LTOP SLRVs or the RCS vent (s) of Specification 3.4.9.3b are used to mitigate an RCS pressure transient, a Special Report I
shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the LTOP SLRVs or-the above RCS vent (s) on the transient, and any corrective action necessary to prevent recurrence.
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HADDAM NECK 3/44-46 Amendment No. 125 O/7k
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Kt'n xo usou REACTOR COOLANT MYSTEM SURVElltANCE REOUIREMENTS
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5 SLRV shall be demonstrated OPERABLE by verifying the Each LTO 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the LTOP SLRV is 4.4.9.3.1 required to be OPERABLEt.open at least once per SLRV isolation valv it oo he RCS vent (s Specificatio
.4.9.3b shaJ1 Mveriff e be 4.4.9.3.2/astoncepe hours when t ent(s) are jb itfg rsed for essure protJet on, except wh he vent pathyaf is provid) with alve e
open g ov t is locked', sealed or othey se secured in,ttie open posiWon.
i Once per COLD SHUTD0k'N, the LTOP System Isolation Valve Interl and Alarms shall be demonstrated OPERABLE by the performance of an A 4.4.9.3.
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CHANNEL OPERATIONAL TEST.
Once per refueling, the LTOP System shall be demonstrate'd OPER by the performance of a CHANNEL CALIBRATION and an ANALOG 4.4.9.3.
TEST.
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Amendment No. 125 3/44-47 HADDAM NECK
y APR 2 61990 REACTOR COOLANT SYSTEM BASES 3/4.4.3 PRESSURIZER The limit on the water level in the pressurizer assures that the parameter is maintained within that assumed in the safety analyses. The 12-hour periodic surveillance is sufficient to ensure that the parameter is restored to within its limit following expected transient operation. The requirement that a minimum number of pressurizer heaters be OPERABLE enhances the capability of the plant to control Reactor Coolant System pressure and establish natural circulation.
3/4.4.4 RELIEF VALVES Operation of the power-operated relief valves (PORVs) minimizes the undesir-able opening of the spring-loaded pressurizer Code safety valves and provide an alternate means of core cooling. Each PORV has a remotely operated block valve to provide a positive shutoff capability should a PORV become ipoper-One of two redundant PORV relief trains must be OPERABLE to adequate-able.
ly cool the core in the event that the steam generators are not avail-able to remove core decay heat.jkWhen in automatic mode, all PORVs and block valves en automatically on high pressurizer pressure. The PORVs and steam bubble gfunction to relieve RCS pressure during all design transients up to and
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including the design step load decrease with steam dump.
i 3/4.4.5 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be The program for inservice inspection of steam generator tubes maintained.
(a) a modification of Regulatory Guide 1.83, Revision 1 and is based on:
(b) Previous Eddy Current Examination results. Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, cr inservice conditions that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.
The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those chemistry limits imposed by plant chemistry guidelines which minimize corrosion of the steam generator tubes.
If the secondary coolant chemistry is not maintained within these limits, localized corrosion may occur. The extent of cracking during plant opera-tion would be limited by the limitation of steam generator tube leakage between the primary coolant system and the secondary system imposed in Operating plants have demon-Specification 3.4.6.2, Operational Leakage.
strated that primary to secondary leakage specified in Specification 3.4.6.2 can readily be detected by radiation monitoring of steam generator blowdown.
Despite chemistry controls, several forms of steam generator corrosion have.
One of the most prevalent forms of been found throughout the industry.
corrosion is wastage, which involves a general thinning of the tube wall b / '2 HADDAM NECK B3/44-3 Amendment No. 125
4 INSERT B With a PORV inoperable and capable of being manually cycled, either the PORV must be restored or the flow path isolated within I hour by closing the associated block valve.
Power must be maintained to the associated block valve, since removal of power would render the block valve inoperable. Although the PORV may be designated inoperable, it is capable of being manually opened and closed and in this manner can be used to perform its function. PORV inoperability may be due to seat leakage, instrumentation problems, automatic control problems, or other causes that will not prevent manual use and will not create a possibility for a small break LOCA. The continued operation of the plant snay continue with the PORV in this inoperable condition for a limited period of time not to exceed the next refueling outage when maintenance can be performed on the PORVs to climinate the degraded condition. The PORVs should normally be availab!c for automatic mitigation of overpressure events and should be returned to OPERABLE status prior to entering startup.
The automatic functioning of the PORVs is to open prior to the pressurizer code safety valves to prevent them from needlessly cycling. The PORVs are not credited as ASME overpressure protection devices.
Quick access to the PORV for manual pressure control or use in emergency procedures'can be made when power remains available for the closed block valve.
If one block valve is inoperabic, then it must be restored to OPERABLE status within one hour, or the associated PORV placed in the closed position. The prime importance for the Therefore, if capability to maintain closed the block valve is to isolate a stuck open PORV.
the block valve cannot be restored to OPERABLE status within I hour, the required action is to place the PORV in the closed position to preclude its automatic opening for an overpressure event and to avoid the potential for a stuck open PORV at a time that the block valve is inoperable. If a block valve is designated inoperable, but can still be manually opened and closed it can be used to perform its function as defined in the f
emergency operating procedures.
Block valve inoperability of this type may be due to leakage, instrumentation problems, automatic control problems, or other causes that sent In this do not prevent manual use and do not create a possibility for a small break LOCA.
condition it is permissible to operate the plant for a limited period of time not to exceed the next refueling outage when corrective maintenance can be performed on the block valve (s). The block valves shall be returned to OPERABLE status prior to entering startup.
If more than one PORV is inoperable and not capable of being manually cycled, it is necessary to either restore at least one valve within the completion time of I hour or isolate the flow path by closing and removing the power to the associated. block valve.
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Docket No. 50-213 B14462 l
Haddam Neck Plant Proposed Revision to Technical Specifications t
Retyped Pages of Technical Specifications L
l May 1993 i
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REACTOR COOLANT SYSTEM 3/4.4.4 RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.4 Both power-operated relief valves (PORVs) and their associated block l
valves shall be OPERABLE. The Setpoint for the PORVs and their block valves shall be greater than or equal to 2325 psig and less than or equal to 2350 psig. The emergency control air supply shall have a minimum pressure of 118 psig.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
a.
With one or both PORV(s) inoperable, and capable of being manually cycled, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to OPERABLE status or close/ verify closed the associated block valve (s) with the power maintained to the block /alve(s); 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 /> and in HOT SHUTDOWN 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 one PORV inoperable and not capable of being manually cycled, l
within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV to OPERABLE status or close/ verify closed the associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within the following 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
l-c.
With both PORVs inoperable and not capable of being manually cycled, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore at least one PORV to OPERABLE status or close/ verify closed both block valves and remove power from the block valves and 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
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d.
With the emergency control air supply pressure for the PORVs less than 118 psig restore the emergency control air supply to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 /> 1
and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
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e.
With one' or both block valves inoperable and not capable of being manually cycled, within 1 bour restore the block valve (s) to OPERABLE status or place is associated PORV(s) controls in the "close" position. Restore at least one block valve to OPERABLE status within the next hour if both block valves are inoperable; restore any remaining inoperable block valve to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; otherwise, be in at least HOT STANDBY within the 4
next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following'6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
f.
With one or more block' valves INOPERABLE and capable of being-i manually cycled, within one hour close the block valve and place its associated PORV in the "close" position.
HADDAM NECK 3/4 4-20 Amendment No. J U,
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1 REACTOR COOLANT SYSTEM SURVEILLANCE RE0VIREMENTS 4.4.4.1 In addition to the requirements of Specification 4.0.5, each PORY shall be demonstrated OPERABLE at least once per 18 months by:
a.
Performance of a CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST, and b.
Operating the valve through one complete cycle of full travel during-Modes 3 or 4.
4.4.4.2 Each PORY block valve shall be demonstrated OPERABLE at least once per 18 months by performance of an ANALOG CHANNEL OPERATIONAL TEST.
4.4.4.3 Each PORV block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed with power removed in order to meet the requirements of ACTION b. or c. in Specification 3.4.4.
4.4.4.4 The control air supply for the PORVs shall be demonstrated OPERABLE at least once per 18 months by verifying that the control air supply does not drop more than 0.3 psi in one hour when isolated from Containment Air Supply System.
4.4.4.5 The air supply for the PORVs shall be verified by local pressure indication once every 92 days.
4.4.4.6 The emergency air supply for the PORVs shall be demonstrated OPERABLE at least once per 18 months by manually transferring the air supply from the normal to the emergency air supply, and operating the valves through a complete cycle of full travel.
HADDAM NECK 3/4 4-21 Amendment No. J7E, 0171
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REACTOR COOLANT SYSTEM LOW TEMPERATURE OVERPRESSURE PROTECTION SYSTEMS t
LIMITING CONDITION FOR OPERATION
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3.4.S.3 At least one of the following Low Temperature Overpressure L
Protection (LTOP) Systems shall be OPERABLE:
a.
Two LTOP spring-loaded relief valves (SLRV) with a lift setting of 380 l
(13%) psig with their respective motor-operated isolation valves in the 1
open position, or I
b.
The Reactor Coolant System (RCS) depressurized with an RCS vent of l
greater than or equal to 7 square inches (3 inches nominal inside I
diameter).
APPLICABILITY:
MODE 4 when the temperature of any RCS cold leg of an unisolated loop is less l
than or equal to 315'F, except during the performance of hydrostatic or leak testing.
MODE 5 and MODE 6 when the head is on the reactor vessel. The l
l overpressure protection system identified in Specification 3.4.9.3.a shall be placed in service prior to placing the RHR system into service and shall remain in service unless the requirements of Specification 3.4.9.3.b are j
satisfied.
1 ACTION:
a.
With one LTOP SLRV inoperable in Mode 4, restore the inoperable LTOP SLRV a
to OPERABLE status within 7 days, or be in COLD SHUTDOWN within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and depressurize and vent the RCS through at least a 7 square inch vent within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of entering COLD SHUTDOWN.
b.
With one LTOP SLRV inoperable in MODES 5 or 6, either (1) restore the inoperable LTOP SLRV 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 (2) complete depressurization and venting of the RCS through at least a 7 square inch vent within a total of 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.
c.
With both LTOP SLRVs inoperable, depressurize and vent the RCS through at l-f least a 7 square inch vent within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
i d.
With the RCS vented per ACTIONS a, b, or c, verify the vent pathway at l.
least once per 31 days when the pathway is provided by a valve (s) that.is locked, sealed, or otherwise secured in the open position; otherwise, verify the vent pathway every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i e.
In the event either the LTOP SLRVs or the RCS vent (s) of Specification l
3.4.9.3b are used to mitigate an RCS pres;ure transient, a Special Report l-shall be prepared and submitted to the Comission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the LTOP SLRVs or the above RCS vent (s) on the transient, and any corrective action necessary to prevent recurrence.
HADDAM NECK 3/4 4-46 Amendment No. JU onn
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REACTOR COOLANT SYSTEM SURVEILLANCE REOUIREMENTS 4.4.9.3.1 Each LTOP SLRV shall be demonstrated OPERABLE by verifying the SLRV isolation valves are open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the LTOP SLRV l
is required to be OPERABLE.
4.4.9.3.2 With the RCS vented per Specification 3.4.9.3.b, verify the vent pathway at least once per 31 days when the pathway is provided by a valve (s) that is locked, sealed, or otherwise secured in the open position; otherwise, verify the vent pathway every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.4.9.3.3 Once per COLD SHUTDOWN, the LTOP System Isolation Valve Interlocks and Alarms shall be demonstrated OPERABLE by the performance of an ANALOG CHANNEL OPERATIONAL TEST.
4.4.9.3.4 Once per refueling, the LTOP System shall be demonstrated OPERABLE by the performance of a CHANNEL CALIBRATION and an ANALOG CHANNEL OPERATIONAL TEST.
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HADDAM NECK 3/4 4-47 Amendment No. JJE 0172 r
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i REACTOR COOLANT SYSTEM BASES l
3/4.4.3 PRESSURIZER The limit on the water level in the pressurizer assures that the parameter is maintained within that assumed in the safety analyses. The 12-hour periodic surveillance is sufficient to ensure that the parameter is restored to within its limit following expected transient operation. The requirement that a minimum number of pressurizer heaters be OPERABLE enhances the capability of the plant to control Reactor Coolant System pressure and establish natural circul ation.
3/4.4.4 RELIEF VALVES Operation of the power-operated relief valves (PORVs) minimizes the undesir-able opening of the spring-loaded pressurizer Code safety valves and provide an alternate means of core cooling. Each PORV has a remotely operated block valve to provide a positive shutoff capability should a PORV become inoper-
[
able. One of two redundant PORV relief trains must be OPERABLE to adequately cool the core in the event that the steam generators are not available to remove core decay heat. With a PORV inoperable and capable of being manually cycled, either the PORY must be restored or the flow path isolated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> by closing the associated block valve.
Power must be maintained to the i
associated block valve, since removal of power would render the block valve l
inoperable. Although the PORV may be designated inoperable, it is capable of l
being manually opened and closed and in this manner can be used to perform its function.
PORV inoperability may be due to seat leakage, instrumentation problems, automatic control probiems, or other causes that will not prevent manual use and will not create a possibility for a small break LOCA. The continued operation of the plant may continue with the PORV in this inoperable i
condition for a limited period of time not to exceed the next refueling outage i
when maintenance can be performed on the PORVs to eliminate the degraded condition. The PORVs should normally be available for automatic mitigation of overpressure events and should be returned to OPERABLE status prior to entering startup.
l The automatic functioning of the PORVs is to open prior to the pressurizer f
code safety valves to prevent them from needlessly cycling. The PORVs are not
.l credited as ASME overpressure protection devices.
Quick access to the PORV for manual pressure control or use in emergency procedures can be made when power remains available for the closed block l
valve.
If one block valve is inoperable, then it must be restored to OPERABLE status within one hour, or the associated PORY placed in the closed position. The prime importance for the capability to maintain closed the block valve is to isolate a stuck open PORV. Therefore, if the block valve cannot be restored to OPERABLE status within I hour, the required action is to place the PORY in j
the closed position to preclude its automatic opening for an overpressure event and to avoid the potential for a stuck open PORV at a time that the HADDAM NECK B3/4 4-3 Amendment No JU 0173
~
REACTOR COOLANT SYSTEM BASES block valve is inoperable.
If a block valve is designated inoperable, but can i
still be manually opened and closed, it can be used to perform its function as defined in the emergency operating procedures. Block valve inoperability of this type may be due to seat leakage, instrumentation problems, automatic control problems, or other causes that do not prevent manual use and do not create a possibility for a small break LOCA.
In this condition it is permissible to operate the plant for a limited period of time not to exceed the next refueling outage when corrective maintenance can be performed on the block valve (s). The block valves shall be returned to OPERABLE status prior to entering startup.
If more than one PORV is inoperable and not capable of being manually cycled, it is necessary to either restore at least one valve within the completion time of I hour or isolate the flow path by closing and removing the power to the associated block valve.
When in automatic mode, all PORVs and block valves open automatically on high pressurizer pressure. The PORVs and steam bubble function to relieve RCS i
pressure during all design transients up to and including the design step load i
decrease with steam dump.
l 1-
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l 3/4.4.5 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes
{
ensure that the structural integrity of this portion of the RCS will be maintained. The program for inservice inspection of steam generator tubes is i
based on:
(a) a modification of Regulatory Guide 1.83, Revision I and (b)
Previous Eddy Current Examination results. Inservice inspection of' steam i
generator tubing is essential in order to maintain surveillance of the j
l conditions of the tubes in the event that there is evidence of mechanical l
damage or progressive degradation due to design, manufacturing arrors, or i
inservice conditions that lead to corrosion.
Inservice inspection of steam t
generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.
The plant is expected to be operated in a manner such that the secondary i
coolant will be maintained within those chemistry limits imposed by plant l
chemistry guidelines which minimize corrosion of the steam generator tubes.
j If the secondary coolant chemistry is not maintained within these limits, localized corrosion may occur. The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage between the l
primary coolant system and the secondary system imposed in Specifica. tion 3.4.6.2, Operational Leakage. Operating plants have demonstrated that primary to secondary leakage specified in Specification 3.4.6.2 can readily be detected by radiation monitoring of steam generator blowdown.
Despite chemistry controls, several forms of steam generator corrosion have been found throughout the industry. One of the most prevalent forms of corrosion is wastage, which involves a general thinning of the tube wall HADDAM NECK B3/4 4-3a Amendment No.
0173
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