ML022070533

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Technical Specification Pages for Millstone - Unit 3, Amendment 206
ML022070533
Person / Time
Site: Millstone Dominion icon.png
Issue date: 07/24/2002
From:
NRC/NRR/DLPM/LPD1
To:
Dominion Nuclear Connecticut
References
TAC MB4011
Download: ML022070533 (34)


Text

REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEM -

SHUTDOWN IYMTING CONDITION FOR OPERATION 3.1.3.3 One digital rod position indicator (excluding demand position indication) shall be OPERABLE and capable of determining the control rod position within +12 steps for each shutdown or control rod not fully inserted.

APPLICABILITY:

MODES 3* **, 4* **, and 5* **

ACTION:

With less than the above required position indicator(s) OPERABLE.

immediately open the Reactor Trip System breakers.

SURVEILLANCE REQUIREMENTS 4.1.3.3 Each of the above required digital rod position indicator(s) shall be determined to be OPERABLE by verifying that the digital rod position indicators agree with the demand position indicators within 12 steps when exercised over the full-range of rod travel at least once per 24 months.

  • With the Reactor Trip System breakers in the closed position.
    • See Special Test Exceptions Specification 3.10.5.

MILLSTONE - UNIT 3 0M34 Amendment No. F9, XfX, 206 3/4 1-24

REACTIVITY CONTROL SYSTEMS ROD DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full-length (shutdown and control) rod drop time from the fully withdrawn position shall be less than or equal to 2.7 seconds from beginning of decay of stationary gripper coil voltage to dashpot entry with:

a.

Tavg greater than or equal to 551'F. and

b.

All reactor coolant pumps operating.

APPLICABILITY:

MODES 1 and 2.

ACTION:

a.

With the drop time of any full-length rod determined to exceed the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.

b.

With the rod drop times within limits but determined with three reactor coolant pumps operating, operation may proceed provided THERMAL POWER is restricted to less than or equal to 65% of RATED THERMAL POWER with the reactor coolant stop valves in the nonoperating loop closed.

SURVEILLANCE REQUIREMENTS z

4.1.3.4 The rod drop time of full-length rods shall be demonstrated through measurement prior to reactor criticality:

a.

For all rods following each removal of the reactor vessel head,

b.

For specifically affected individual rods following any maintenance on or modification to the Control Rod Drive System which could affect the drop time of those specific rods, and

c.

At least once per 24 months.

MILLSTONE - UNIT 3 3/4 1-25 Amendment No.

9, Xfl,206 o043

REACTOR COOLANT SYSTEM RELIEF VALVES SURVEILLANCE REQUIREMENTS 4.4.4.1 In addition to the requirements zf Specification 4.0.5, each PORV shall be demonstrated OPERABLE by:

a.

Performance of a CHANNEL CALIBRATION at least once per 24 months: and

b.

Operating the valve through one complete cycle of full travel during MODES 3 or 4 at least once per 24 months; and

c.

Performance of an ANALOG CHANNEL OPERATIONAL TEST on the PORV high pressurizer pressure actuation channels, but excluding valve operation.

at least once each quarter; and

d.

Verify the PORV high pressure automatic opening function is enabled at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.4.4.2 Each 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.

4.4.4.3 The emergency power supply for the PORVs and block valves shall be demonstrated OPERABLE at least once per 24 months by operating the valves through a complete cycle of full travel.

MILLSTONE -

UNIT 3 0846 3/4 4-13 Amendment No.

FF, M,

WI,,206

REACTOR COOLANT SYSTEM 314.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System Leakage Detection Systems shall be OPERABLE:

a.

Either the Containment Atmosphere Gaseous or Particulate Radioactivity Monitoring System, and

b.

The Containment Drain Sump Level or Pumped Capacity Monitoring System APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

a.

With both the Containment Atmosphere Gaseous and Particulate Radioactivity Monitors INOPERABLE, operation may continue for up to 30 days provided the Containment Drain Sump Level or Pumped Capacity Monitoring System is OPERABLE and gaseous grab samples of the containment atmosphere are obtained at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and analyzed for gross noble gas activity within the subsequent 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />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 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 the Containment Drain Sump Level or Pumped Capacity Monitoring System INOPERABLE, operation may continue for up to 30 days provided either the Containment Atmosphere Gaseous or Particulate Radioactivity Monitoring System is OPERABLE; 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 COLD SHUTDOWN within the followng 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.6.1 The Leakage Detection Systems shall be demonstrated OPERABLE by:

a.

Containment Atmosphere Gaseous and Particulate Radioactivity Monitoring Systems-performance of CHANNEL CHECK, CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST at the frequencies specified in Table 4.3-3, and

b.

Containment Drain Sump Level and Pumped Capacity Monitoring System performance of CHANNEL CALIBRATION at least once per 24 months.

MILLSTONE - UNIT 3 3/4 4-21 Amendment No. P, 79, 0, 1;;, 206 0947

REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE SURVEILLANCE REQUIREMENTS 4.4.6.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:

a.

Monitoring the containment atmosphere (gaseous or particulate) radioactivity monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />;

b.

Monitoring the containment drain sump inventory and discharge at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />;

c.

Measurement of the CONTROLLED LEAKAGE to the reactor coolant pump seals when the Reactor Coolant System pressure is 2250 +/- 20 psia at least once per 31 days with the modulating valve fully open.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4;

d.

Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and

e.

Monitoring the Reactor Head Flange Leakoff System at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated OPERABLE by verifying leakage to be within its limit:

a.

At least once per 24 months,

b.

Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 7 days or more and if leakage testing has not been performed in the previous 9 months,

c.

Prior to returning the valve to service following maintenance, repair or replacement work on the valve,

d.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following valve actuation due to automatic or manual action or flow through the valve, and

e.

When tested pursuant to Specification 4.0.5.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.

MILLSTONE - UNIT 3 3/4 4-23 Amendment No. ;90,

79, 206

REACTOR COOLANT SYSTEM OVERPRESSURE PROTECT ION SYSTEM SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Demonstrate that each required PORV is OPERABLE by:

a.

Performance of an ANALOG CHANNEL OPERATIONAL TEST on the PORV actuation

channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORV is required OPERABLE and at least once per 31 days thereafter when the PORV is required OPERABLE;
b.

Performance of a CHANNEL CALIBRATION on the PORV actuation channel at least once per 24 months; and

c.

Verifying the PORV block valve is open and the PORV Cold Overpressure Protection System (COPPS) is armed 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 PORV is being used for overpressure protection.

4.4.9.3.2 Demonstrate that each required RHR suction relief valve is OPERABLE by:

a.

Verifying the isolation valves between the RCS and each required RHR suction relief valve are open at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; and

b.

Testing pursuant to Specification 4.0.5.

When complying with 3.4.9.3.4, verify that the RCS is vented through a vent pathway > 2.0 square inches at least once p~e 31 days for a passive vent path 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 /> for unlocked open vent valves.

Verify that no Safety Injection pumps are capable of injecting into the RCS at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Verify that a maximum of one centrifugal injecting into the RCS at least once per charging pump is capable of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Amendment No. 79, 09, 109, 7P, 1J7, IF7,206 4.4.9.3.3 4.4.9.3.4 4.4.9.3.5 MILLSTONE - UNIT 3 3/4 4-39 089

SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE

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 \\erlying that are in the indicated positions with power to removed:

the following valves the valve oDerators Valve Number 3SIH*MV8806 3SIH*MV8802A 3SIH*MV8802B 3SIH*MV8835 3SlH*MV8813 3SlL*MV8840 3S1L*MV8809A 3SlL*MV8809B Valve Function RWST Supply to Si PuMps SI Pump A to Hot Leg Injection SI Pump B to Hot Leg Injection SI Cold Leg Master Isolation SI Pump Master Miniflow Isolation RHR to Hot Leg Injection RHR Pump A to Cold Leg Injection RHR Pump B to Cold Leg Injection Valve Position OPEN CLOSED CLOSED OPEN OPEN CLOSED OPEN OPEN

b.

At least once per 31 days by:

1) Verifying that the ECCS piping, except for the operating centrifugal charging pump(s) and associated piping, the RSS
pump, the RSS heat exchanger and associated piping. is full of water, and
2)

Verifying that each valve (rn.nual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

By a

.,sual inspection which verifies tnat no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.

This visual inspection shall be performed:

1)

For all accessible areas of the containment prior to establish ing CONTAINMENT INTEGRITY, and

2)

At least once daily of the areas affected (during each day) within containment by containment entry and during the final entry when CONTAINMENT INTEGRITY is established.

d.

At least once per 24 months by:

1)

Verifying automatic interlock action of the RHR System from the Reactor Coolant System by ensuring that with a simulated signal greater than or equal to 412.5 psia the interlocks prevent the valves from being opened.

MILLSTONE -

UNIT 3 0851 3/4 5-4 Amendment No. 00, 79, 9,w WZ, 717.

1J9,206 I

SURVEILLANCE REQUIREMENTS (Continued)

2)

A visual inspection of tL7 containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components 'trash racks, screens, etc.) show no evidence of structural distress or abnormal corrosion.

e.

At least once per 24 months by:

1) Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection actuation test signal, and
2)

Verifying that each of the following pumps start automatically upon receipt of a Safety Injection actuation test signal:

a)

Centrifugal charging pump, b)

Safetv Injection pump, and c)

RHR pump.

3)

Verifying that the Residual Heat Removal pumps stop automatically upon receipt of a Low-Low RWST Level test signal.

f.

By verifying that each of the following pump's developed head at the test flow point is greater than or equal to the required developed head when tested pursuant to Specification 4.0.5:

1) Centrifugal charging pump
2)

Safety Injection pump

3)

RHR pump

4)

Containment recirculation pump

g.

By verifying the correct position of each electrical and/or mechanical position stop for the following ECCS throttle valves:

1) Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE, and
2)

At least once per 24 months.

ECCS Throttle Valves Valve Number Valve Number 3SlH*V6 3SIH*V25 3SIH*V7 3SIH*V27 Amendment No.

09, 1?#, YJF, 206 MILLSTONE - UNIT 3 0851 3/4 5-5

EMERGENCY CORE COOLING SYSTEMS 3/4.5.5 pH TRISODIUM PHOSPHATE STORAGE BASKETS LIMITING CONDITION FOR OPERATION The trisodium phosphate (TSP, dodecahydrate Storage Baskets shall be APPLICABILITY:

MODES 1. 2. 3 and 4 ACTION:

With the TSP Storage Baskets inoperable, restore the system TSP Storage Baskets 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 HOT SHUTDOWN the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.5.5 The TSP Storage Baskets shall be demonstrated OPERABLE at least once per 24 months by verifying that a minimum total of 974 cubic feet of TSP is contained in the TSP Storage Baskets.

MILLSTONE UNIT NO.

3 0852 3/4 5-10 Amendment No. 77,-206 3.5.5 OPERABLE.

CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT QUENCH SPRAY SYSTEM LIMITING CONDITION FOR OPERATION Two independent Containment Ouench Spray subsystems shall APPLICABILITY:

MODES 1, 2. 3. and 4.

ACTION:

With one Containment Quench Spray subsystem inoperable, restore the inoperable system 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 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 Each Containment Quench Spray subsystem shall be demonstrated

a.

At least once per 31 days:

1) Verifying that each valve (manual, power
operated, or automatic) in the flow path that is not locked,
sealed, or otherwise secured in position, is in its correct position; and
2)

Verifying the temperature of the borated water in the refueling water storage tank is between 40°F and 50°F.

b.

By verifying that each pump's developed head at the test flow point is greater than or equal to the required developed head when tested pursuant to Specification 4.0.5;

c.

At least once per 24 months, by:

1) Verifying that each automatic valve in the flow path actuates to its correct position on a CDA test signal, and
2)

Verifying that each spray pump starts automatically on a CDA test signal.

d.

At least once through each unobstructed.

MILLSTONE - UNIT 3 0853 per 10 years by performing an air or smoke flow test spray header and verifying each spray nozzle is 3/4 6-12 Amendment No. P, P, 199, Mf,

IJP,
77, 206 3.6.2.1 OPERABLE.

be 4.6.2.1 OPERABLE:

CONTAINMENT SYSTEMS RECIRCULATION SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.2 Two independent Recirculation Spray Systems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2. 3. and 4.

ACTION:

With one Recirculation Spray System inoperable. restore the inoperable System 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 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 />; restore the inoperable Recirculation Spray System to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be 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 4.6.2.2 Each Recirculation Spray System shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power operated, or automatic) in the flow path that is not locked, sealed.

or otherwise secured in position, is in its correct position;

b.

By verifying that each pump's developed head at the test flow point is greater than or equal to the required developed head when tested pursuant to Specification 4.0.5;

c.

At least once per 24 months by verifying that on a CDA test signal, each recirculation spray pump starts automatically after a 660 +20 second delay;

d. At least once per 24 months. by verifying that each automatic valve in the flow path actuates to its correct position on a CDA test signal:

and

e.

At least once through each unobstructed.

per 10 years by performing an spray header and verifying air or smoke flow test each spray nozzle is MILLSTONE - UNIT 3 0053 3/4 6-13 Amendment No. P9, lop, 17?,

IPP, 777, 206

CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 The containment isolation valves shall be OPERABLE* with isolation times less than or equal to the required isolation times.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With one or more of the isolation valve(s) inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and:

a.

Restore the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or

b.

Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or

c.

Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange; or

d.

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 4.6.3.1 DELETED 4.6.3.2 Each isolation valve shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 24 months by:

a.

Verifying that on a Phase "A" Isolation test signal, each isolation valve actuates to its isolation position,

b.

Verifying that on a Phase "B" Isolation test signal, each isolation valve actuates to its isolation position, and Phase "A" Phase "B"

c.

Verifying that on a Containment High Radiation test signal, each purge supply and exhaust isolation valve actuates to its isolation position.

4.6.3.3 The isolation time of each power-operated or automatic valve shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

  • The provisions of this Specification are not applicable for main steam line isolation valves.

However, provisions of Specification 3.7.1.5 are applicable for main steam line isolation valves.

MILLSTONE - UNIT 3 0929 3/4 6-15 Amendment No. IF, 97, P7,

pplXJJ, 111.I jZp*lo.

20 6 I

CONTAINMENT SYSTEMS ELECTRIC HYDROGEN RECOMBINERS LIMITING CONDITION FOR OPERATION 3.6.4.2 Two independent Hydrogen RecoTbirer Systems shall be OPERABLE.

APPLICABILITY:

MODES I and 2.

ACTION:

With one Hydrogen Recombiner System inoperable, restore the inoperable system to OPERABLE status within 30 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 />.

SURVEILLANCE REQUIREMENTS 4.6.4.2 Each Hydrogen Recombiner System shall be demonstrated OPERABLE at least once per 24 months by:

a.

Deleted

b.

Performing a CHANNEL CALIBRATION of all recombiner instrumentation and control circuits,

c.

Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiner enc'osure (i.e.,

loose wiring or structural connections, deposits of foreign materials.

etc.).

d.

Verifying the integrity of all heater electrical circuits by performing a resistance to ground test following the above required functional test.

The resistance to ground for any heater phase shall be greater than 10,000 ohms, and

e.

Verifying during a recombiner system functional test using containment atmospheric air at an acceptable flow rate as determined in Section 4.6.4.2.f that the gas temperature increases to greater than or equal to 1100°F within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and is maintained for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

f.

Verifying during a recombiner system functional test using containment atmospheric air that the blower would be capable of delivering at least 41.52 scfm at containment conditions of 12.47 psia and 1300F.

MILLSTONE -

UNIT 3 0854 3/4 6-17 Amendment No. 07,

, 700, 1l7, 206

CONTAINMENT SYSTEMS 3/4.6.6 SECONDARY CONTAINMENT SUPPLEMENTARY LEAK COLLECTION AND RELEASE SYSTEM LIMITING CONDITION FOR OPERATION 3.6.6.1 Two independent Supplementary LeaK Collection and Release Systems shall be OPERABLE with each system comprised of:

a.

one OPERABLE filter and fan, and

b.

one OPERABLE Auxiliary Building Filter System as defined in Specification 3.7.9.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With one Supplementary Leak Collection and Release System inoperable, restore the inoperable system 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 />.

SURVEILLANCE REQUIREMENTS 4.6.6.1 Each Supplementary Leak Collection and Release System shall be demon strated OPERABLE:

a.

At least once per 31 days on a STAGGERE.

TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying 7 system flow rate of 7600 cfm to 9800 cfm and that the system operates for at least 10 continuous hours with the heaters operating.

b.

At least once per 24 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 communi cating with the system by:

1)

Verifying that the system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% and uses the test procedure guidance in Regulatory Posi tions C.5.a, C.5.c, and C.5.d of Regulatory Guide 1.52, Revi sion 2, March 1978,* and the system flow rate is 7600 cfm to 9800 cfm; MILLSTONE - UNIT 3 3/4 6-19 Amendment No. 7, M l 7, 0o55 09,, 11;, 206

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

2)

Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accord ance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2. March 1978,* Shows the methyl iodide penetration less than or equal to 2.5' when tested in accordance with ASTM D3803-89 at a temperature of 30-C (86°F) and a relative humidity of 70%; and

3)

Verifying a system flow rate of 7600 cfm to 9800 cfm during syste operation when tested in accordance with ANSI N510-1980.

c.

After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation, by verifying, within 31 days after removal that a laboratory analysis of a repre sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52. Revision 2, March 1978,* shows the methyl iodide penetration less than or equal to 2.5% when tested in accordance with ASTM D3803-89 at a temperature of 30°C (86°F) and a relative humidity of 70%:

d.

At least once per 24 months by:

1)

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6.25 inches Water Gauge while operating the system at a flow rate of 7600 cfm to 9800 cfm,

2)

Verifying that the system starts on a Safety Injection test

signal, and
3)

Verifying that the heaters dissipate 50 +5 kW when tested in accordance with ANSI N510-1980.

  • ANSI N510-1980 shall be used in place of ANSI N510-1975 referenced in Regulatory Guide 1.52, Revision 2, March 1978.

MILLSTONE - UNIT 3 3/4 6-20 Amendment No.

1, 0, 97, 085S 799, ;?;, fl9, IF#, 206

CONTAINMENT SYSTEMS SECONDARY CONTAINM4ENT LIMITING CONDITION FOR OPERATION 3.6.6.2 Secondary Containment shall be OPERABLE.

APPLICABILITY:

MODES 1. 2, 3. and 4.

ACTION:

With Secondary Containment inoperable, restore Secondary Containment 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 />.

SURVEILLANCE REQUIREMENT 4.6.6.2.1 OPERABILITY of Secondary Containment shall be demonstrated at least once per 31 days by verifying that each door in each access opening is closed except when the access opening is being used for normal transit entry and exit.

4.6.6.2.2 At least once per 24 months, verify each Supplementary Leak Collection and Release System produces a negative pressure of greater than or equal to 0.4 inch water gauge in the Auxiliary Building at 24'-6" elevation within 120 seconds after a start signal.

3/4 6-22 Amendment No. 07,

lop, Wi, JF, 206 MILLSTONE - UNIT 3 08se

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

b.

At least once per 92 days on a STAGGERED TEST BASIS. tested pursuant to Specification 4.0.5.

'Oy:

I)

Verifying that.,n recirculation fltiow each -otor-driven pump develops a tota head of greater than or equal to 3385 feet:

2)

Verifying that on -ecirculation flow !the steam turbine-driven pump develops a total head of greater than or equal to 3780 feet when the secondary steam supply pressure is greater than 800 psig.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

c.

At least once per 24 months by verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of an Auxiliary Feedwater Actuation test signal.

For the steam turbine driven auxiliary feedwater pump, the provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

4.7.1.2.2 An auxiliary feedwater flow path to each steam generator shall be demonstrated OPERABLE following each COLD SHUTDOWN of greater than 30 days prior to entering MODE 2 by verifying flow to each steam generator.

MILLSTONE - UNIT 3 0857 3/4 7-5 Amendment No. 9, 719, 7*7, 119, 206

PLANT SYSTEMS 3/4.7.3 REACTOR PLANT COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3 At least two independent reactor p ant co0ocnent co...

ater saFety loops shall be OPERABLE.

APPLICABILITY:

MODES 1. 2. 3, rd an ACTION:

With only one reactor plant component cooling water safety loop OPERABLE, re store at least two loops 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 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 followinq 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.7.3 At least two reactor plant component cooling water safety loops shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) servicing safety-related equipment that is not locked, sealed, or otherwise secured in position is in its correct position; and

b.

At least once per 24 months by verifying that:

1)

Each automatic valve actuates to its correct position on its associated Engineered Safety Feature actuation signal, and

2)

Each Component Cooling Water System pump starts automatically on an SIS test signal.

'/A 7-11 Amendment No.

177,206 MILL31UIWrL -

unlz 0

o0ss

.,r / -,r

  • PLANT SYSTEMS 3/4.7.4 SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4 At least two independent service 1.,*.er iocps shall L- -2ERABLE.

APPLICABILITY:

MODES 1. 2, 3. and 4.

ACTION:

With only one service water loop OPERABLE, restore at least two loops 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 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 4.7.4 At least two service water loops shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power-operated. or automatic) servicing safety-related equipment that is not locked, sealed. or otherwise secured in position is in its correct position: and

b.

At least once per 24 months by verifying that:

1)

Each automatic valve servicing safety-related equipment actuates to its correct position on its associated Engineered Safety Feature actuation signal, and

2)

Each Service Water System pump starts SIS test signal.

3/4 7-12 automatically on an Amendment No. 777, 206 MILLSTONE -

UNIT 3 0858

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.7 Each Control Room Emergency Air Filtration System shall be demonstrated OPERABLE:

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 control room air temperature is less than or equal to 95°F;

b.

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 a system flow rate of 1,120 cfm +20% and that the system operates for at least 10 continuous hours with the heaters operating;

c.

At least once per 24 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 with the system by:

1)

Verifying that the system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% and uses the test procedure guidance in Regulatory Position C.5.a, C.5.c, and C.5.d of Regulatory Guide 1.52, Revisions 2, March 1978,* and the system flow rate is 1,120 cfm +20%;

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,*

shows the methyl iodide penetration less than or equal to 2.5% when tested in accordance with ASTM D3803-89 at a temperature of 300C (860F),

a relative humidity of 70%,

and a face velocity of 54 ft/min; and

3)

Verifying a system flow rate of 1,120 cfm +20% during system operation when tested in accordance with ANSI N510-1980.

d.

After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation, by 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,*

shows the methyl iodide penetration less than or equal to 2.5% when tested in accordance with ASTM D3803-89 at a temperature of 30C (86°F),

and a relative humidity of 70%, and a face velocity of 54 ft/min.

e.

At least once per 24 months by:

1)

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6.75 inches Water Gauge while operating the system at a flow rate of 1,120 cfm +/-20%;

MILLSTONE - UNIT 3 3/4 7-16 Amendment No. 2, ly, X7, T*,

0930 Xp;, 206

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.8 Each Control Room Envelope Pressurization System shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying that the storage air bottles are pressurized to greater than or equal to 2200 psig,

b.

At least once per 31 days on a STAGGERED TEST BASIS by verifying that each valve (manual, power operated or automatic) in the flow path not locked, sealed or otherwise secured in position, is in its correct position, and

c.

At least once per 24 months or following a major alteration of the control room envelope pressure boundary by:

1.

Verifying that the control room envelope is isolated in response to a Control Building Isolation test signal,

2.

Verifying that after a 60 second time delay following a Control Building Isolation test signal, the control room envelope pressurizes to greater than or equal to 1/8 inch W.G. relative to adjacent areas and outside atmosphere, and

3.

Verifying that the positive pressure of Specification 4.7.8.c.2 is maintained for greater than or equal to 60 minutes.

Amendment No. JXP, N 206 MILLSTONE -

UNIT 3 0931 3/4 7-19

PLANT SYSTEMS 3/4.7.9 AUXILIARY BUILDING FILTER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.9 Two independent Auxiliary Building Filter Systems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With one Auxiliary Building Filter System inoperable, restore the inoperable system 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 />.

In

addition, comply with the ACTION requirements of Specification 3.6.6.1.

SURVEILLANCE REQUIREMENTS 4.7.9 Each Auxiliar Building Filter System 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 a system flow rate of 30,000 cfm +10% and that the system operates for at least 10 continuous hours with the heaters operating;
b.

At least once per 24 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 with the system by:

1)

Verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% and uses the test procedure guidance in 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 30,000 cfm +/-10%;

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,* shows the methyl MILLSTONE -

UNIT 3 3/4 7-20 Amendment No. 7, 07, P, XI",

0931 lp;, 206

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS iodide penetration less than or equal to 2.5% when tested in accordance w.ith ASTŽ,! 3i03-29 at a te-perature of 30'C (866F), a relati,.e huri.*tvy Df *.

and a race velocity of 52 ft/mmn: and

3)

Verifying a system f rc.

,-ate

F 30.000
-f-

-103/4, uring system operation when reated in acccrdance

..ith ANSI N510-i980.

c.

After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation, by 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,*

shows the methyl iodide penetration less than or equal to 2.5% when tested in accordance with ASTM D3803-89 at a temperature of 30*C (86°F),

a relative humidi t y of 70%,

and a face velocity of 52 ft'min:

d.

At least once per 24 months by:

1)

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6.8 inches Water Gauge while operating the system at a flow rate of 30,000 cfm +10%,

2)

Verifying that the system starts on a Safety Injection test signal, and

3)

Verifying that the heaters dissipate 180

+18 kW when tested in accordance with ANSI N510-1980.

e.

After each complete or partial replacement of a HEPA filter bank, by verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% in accordance with ANSI N510-1980 for a DOP test aerosol while operating the system at a

flow rate of 30,000 cfm +10%; and

f.

After each complete or partial replacement of a

charcoal adsorber bank, by verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 30,000 cfm +10%.

ANSI N510-1980 shall be used in place of ANSI N510-1975 referenced in Regulatory Guide 1.52, Revision 2, March 1978.

MILLSTONE - UNIT 3 3/4 7-21 Amendment No. 7, 07, M, 09, 206 0860

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) type that may be generically susceptible: and (2) the affected snubber is functionally testei in the as-found condition and determined OPERABLE per Specification 4.7.10.f.

All snubbers found connected to an inoperable common hydraulic fluid reservoir shall be counted as unacceptable for determining the next inspection interval.

A review and evaluation shall be performed and documented to justify continued operation dith an unacceptable snubber.

if continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met.

d.

Transient Event Inspection An inspection shall be performed of all snubbers attached to sections of systems that have experienced unexpected, potentially damaging transients as determined from a review of operational data and a visual inspection of the systems within 6 months following such an event.

In addition to satisfying the visual inspection acceptance criteria, freedom-of-motion of mechanical snubbers shall be verified using at least one of the following:

(1) manually induced snubber movement, or (2) evaluation of in-place snubber piston setting; or (3) stroking the mechanical snubber through its full range of travel.

e.

Functional Tests During the first refueling shutdown and at least once per 24 months thereafter,* a representative sample of snubbers of each type shall be tested using one of the following sample plans. The sample plan for each type shall be selected prior to the test period and cannot be changed during the test period.

The NRC Regional Administrator shall be notified in writing of the sample plan selected for each snubber type prior to the test period or the sample plan used in the prior test period shall be implemented:

1) At least 10% of the total of each type of snubber shall be functionally tested either in-place or in a bench test.

For each snubber of a type that does not meet the functional test acceptance criteria of Specification 4.7.10f., an additional 5%

of that type of snubber shall be functionally tested until no more failures are found or until all snubbers of that type have been functionally tested; or

  • Except the surveillance related to snubber functional testing due no later than March 10, 1999 may be deferred until the end of the next refueling outage or no later than September 10, 1999, whichever is earlier.

MILLSTONE - UNIT 3 0861 3/4 7-23 Amendment 97, 7F, x7, 777, IF7, 206

REFUELING OPERATIONS 3/4.9.12 FUEL BUILDING EXHAUST FILTER SYSTEM LIMITING CONDITION FOR OPERATION 3.9.12 Two independent Fuel Building Exhaust Filter Systems shall be OPERABLE.#

At least one Fuel Building Exhaust Filter System shall be in operation whenever any evolution involving movement of fuel within the storage pool or crane operations with loads over the storage pool is in progress.

APPLICABILITY:

Whenever irradiated fuel with less than 60 days decay is in the storage pool.

ACTION:

a.

With one Fuel Building Exhaust Filter System inoperable, fuel movement within the storage pool or crane operation with loads over the storage pool may proceed'provided the OPERABLE Fuel Building Exhaust Filter System is capable of being powered from an OPERABLE emergency power source and is in operation and discharging through at least one train of HEPA filters and charcoal adsorbers.

b.

With no Fuel Building Exhaust Filter System OPERABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool until at least one Fuel Building Exhaust Filter System is restored to OPERABLE status.

c.

The provisions of Specifications 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.12.1 The above required Fuel Building Exhaust Filter Systems shall be demonstrated OPERABLE:

a.

Within 31 days prior to moving fuel within or loads over the storage pool when irradiated fuel with less than 60 days decay is present by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers, and verifying a system flow rate of 20,700 cfm

+10% and that the system operates for at least 10 continuous hours with the heaters operating;

b.

At least once per 24 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 with the system by:

The Fuel Building boundary may be opened intermittently under administrative control.

MILLSTONE - UNIT 3 3/4 9-13 Amendment No. 1, $7, IFF, Wl, 0932 y77, 0 206

REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued)

1)

Verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% and uses the test procedure guidance in Regulatory Positions C.5.. C.5.c,.

and C.5.d of Regulatory Guide 1.52, Revision 2. March 1978,* and the syster flow rate is 20.700 cfm -10i:

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,*

shows the methyl iodide penetration less than or equal to 2.5% when tested in accordance with ASTM D3803-89 at a temperature of 30°C (86°F) and a relative humidity of 70%; and

3)

Verifying a system flow rate of 20,700 cfm +10% during system operation when tested in accordance with ANSI N510-1980.

c.

After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by 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,*

shows the methyl iodide penetration less than or equal to 2.5% when tested in accordance with ASTM D3803-89 at a temperature of 30°C (86°F) and a relative humidity of 70%;

d.

At least once per 24 months by:

1) Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than.6.8 inches Water Gauge while operating the system at a flow rate of 20,700 cfm +10%.

MILLSTONE - UNIT 3 3/4 9-14 Amendment No. X, 1Z*, J*, 206 0862

3A4.0 APPLiCABiLiTI BASES "Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components is maintained, that facility operation will be within safety lIimits. and thnt the limiting conditions of operation will be met."

Soecification 4.0.1 establishes the requirement that surveillances 'ust be performe during the OPERATIONAL MODES or other conditions for w,;hich the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement.

The purpose of this specification is to ensure that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in a MODE or other specified condition for which the associated Limiting Conditions for Operation are applicable.

Surveillance requirements do not have to be performed when the facility is in an OPERATIONAL MODE for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified.

The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a specification.

Specification 4.0.2 This specification establishes the limit for which the specified time interval for surveillance requirements may be extended.

It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance: e.g., transient conditions or other ongoing surveillance or maintenance activities.

It also provides flexibility to accommodate the length of a fuel cycle for surveillances that are performed at each refueling outage and are specified typically with an 18-month surveillance interval.

It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outage.

The limitation of 4.0.2 is based on engineering judgment and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the surveillance requirements.

This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

Specification 4.0.3 establishes the failure to perform a

Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.

Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval.

However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements.

This specification also clarifies that the ACTION requirements are applicable when the Surveillance Requirements have not MT1ICTnur lIMIT 1 8 314 0-4 Amendment No. 07, 177, 206 09863

REACTOR COOLANT SYSTEM BASES OVERPRESSURE PROTECTION SYSTEMS (continued)

Performance of a CHANNEL CALIBRATION on eacn required PORV actuation channel is required once per 24 months to adjust the :hanne! so that it responds and the valve opens within the required range and accuracy to a known input.

The PORV block valve must be verified open and COPPS must be verified armed every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to provide a flow path and a cold overpressure protection actuation circuit for each required PORV to perform its function when required.

The valve is remotely verified open in the main control room.

This Surveillance is performed if credit is being taken for the PORV to satisfy the LCO.

The block valve is a remotely controlled, motor operated valve.

The power to the valve operator is not required to be removed, and the manual operator is not required to be locked in the open position.

Thus, the block valve can be closed in the event the PORV develops excessive leakage or does not close (sticks open) after relieving an overpressure transient.

The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Frequency is considered adequate in view of other administrative controls available to the operator in the control room, such as valve position indication, that verify the PORV block valve remains open.

4.4.9.3.2 Each required RHR suction relief valve shall be demonstrated OPERABLE by verifying the RHR suction valves, 3RHS*MV87O1A and 3RHS*M8701C, are open when suction relief valve 3RHS*RV8708A is being used to meet the LCO and by verifying the RHR suction valves, 3RHS*MV8702B and 3RHS*MV8702C, are open when sucti n relief valve 3RHS*RV8708B is being used to meet the LCO.

Each required RHR suction relief valve shall also be demonstrated OPERABLE by testing it in accordance with 4.0.5. This Surveillance is only required to be performed if the RHR suction relief valve is being used to meet this LCO.

The RHR suction valves areverified to be open every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The Frequency is considered adequate in view of other administrative controls such as valve status indications available to the operator in the control room that verify the RHR suction valves remain open.

The ASME Code,Section XI (Ref.

9), test per 4.0.5 verifies OPERABILITY by proving proper relief valve mechanical motion and by measuring and, if required, adjusting the lift setpoint.

MTIIq;TfMF - UNIT 3 B 3/4 4-25 Amendment No.

WJi, 1*7, 206 0884

EMERGENCY CORE IUULlIN6 fILL-.

BASES (continued)

APPLICABILITY In MODES 1. 2, 3. and 4, a design basis accident (DBA) could lead to a fission product release to containment tha: leaks to the secondary containment boundary.

The large brea'z LOCA.

on which this system's design,s based. is a full-power event.

Less severe LOCAs and Ieakage ;tili require the system to be OPERABLE throughout these MODES.

The probabilit',ý and severity' of a LOCA decrease as core power and reactor coolant system pressure Jecrease.

With the reactor shut down, the probability of release of radioactivity resulting from such an accident is low.

In MODES 5 and 6, the probability and consequence of a DBA are low due to the pressure and temperature limitations in these MODES.

Under these conditions, the SLCRS is not required to be OPERABLE.

ACT-IONS If it is discovered that the TSP in the containment building sump is not within limits, action must be taken to restore the TSP to within limits.

During plant operation, the containment sump is not accessible and corrections may not be possible.

The 7-day Completion Time is based on the low probability of a DBA occurring during this period.

The Completion Time is adequate to restore the volume of TSP to within the technical specification limits.

If the TSP cannot be restored within limits within the 7-day Completion Time, the plant must be brought to a MODE in which the LCO does not apply.

The specified Completion Times for reaching MODES 3 and 4 are those used throughout the technical specificatinns; they were chosen to allow reaching the specified conditions from full power in an orderly manner and without challenging plant systems.

SURVEILLANCE REQUIREMENTS Surveillance Requirement 4.5.5 Periodic determination of the volume of TSP in containment must be performed due to the possibility of leaking valves and components in the containment building that could cause dissolution of the TSP during normal operation.

A Frequency of once per 24 months is required to determine visually that a minimum of 974 cubic feet is contained in the TSP Storage Baskets.

This requirement ensures that there is an adequate volume of TSP to adjust the pH of the post LOCA sump solution to a value Ž 7.0.

The periodic verification is required every refueling outage, since access to the TSP baskets is only feasible during outages.

Operating experience has shown this Surveillance Frequency acceptable due to the margin in the volume of TSP placed in the containment building.

TUT?*

Un I

R 3/4 5-5 Amendment No.

X70, 206 Os.'

CONTAINMENT SYSTEMS BASES 3/4.6.6.1 SUPPLEMENTARY LEAK COLLECTION AND RELEASE SYSTEM (Continued)

Surveillance Reauirements a

Cumulative operation of the SLCRS with heaters operating for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.

The 31-day frequency was developed in consideration of the known reliability of fan motors and con trols.

This test is performed on a STAGGERED TEST BASIS once per 31-days.

b. c. e, and f These surveillances verify that the required SLCRS filter testing is performed in accordance with Regulatory Guide 1.52, Revision 2.

ANSI N510-1980 shall be used in place of ANSI N510-1975 referenced in Regulatory Guide 1.52, Revision 2.

Laboratory testing of methyl iodide penetration shall be performed in accordance with ASTM D3803-89 and Millstone Unit 3 specific parameters.

The surveillances include testing HEPA filter performance, charcoal adsorber efficiency, system flow rate, and the physical properties of the activated charcoal (general use and following specific operations).

The heater kW measured must be corrected to its nameplate rating.

Variations in system voltage can lead to measurements of kW which cannot be compared to the nameplate rating because the output kW is proportional to the square of the voltage.

The 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of operation requirement originates from Regulatory Guide 1.52, Revision 2, March 1978, Table 2, Note "c", which states that "Testing should be performed (1) initially, (2) at least once per 18 months thereafter for systems maintained in a standby status or after 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operations, and (3) following painting, fire, or chemical release in any ventilation zone communicating with *he system."

This testing ensures that the charcoal adsorbency capacity has not degraded below acceptable limits, as well as providing trend data.

The 720 hour0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> figure is an arbitrary number which is equivalent to a 30 day period.

This criteria is directed to filter systems that are normally in operation and also provide emergency air cleaning functions in the event of a Design Basis Accident.

The applicable filter units are not normally in operation and the sample canisters are typically removed due to the 18 month criteria.

d The automatic startup ensures that each SLCRS train responds properly.

The once per 24 months frequency is based on the need to perform this surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the surveillance was performed with the reactor at power.

The surveillance verifies that the SLCRS starts on a SIS test signal.

It also includes the automatic functions to isolate the other ventilation systems that are not part of the safety-related postaccident operating configuration and to start up and to align the ventilation systems MILLSTONE - UNIT 3 B 3/4 6-6 Amendment No. 07, W*,

70f, 206 0933

BASES 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM (Continued)

SURVEILLANCE REQUIREMENTS (Continued) 4.7.7.c The performance of the control room e~rergency filtration systems should be checked periodically by verifying the HEPA Filter efficiency, charcoal adsorber efficiency, minimum flow rate. and the physical properties of the activated charcoal.

The frequency is at least once per 24 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 with the system.

ANSI N510-1980 will be used as a procedural guide for surveillance testing.

4.7.7.c.1 This surveillance verifies that the system satisfies the in-place penetratica and bypa.s leakage testing acceptance criterion of less than 0.05% in accordance with Regulatory Position C.5.a, C.5.c, and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, while operating the system at a flow rate of 1,120 cfm +/- 20%.

ANSI N510-1980 is used in lieu of ANSI N510-1975 referenced in the regulatory guide.

4.7.7.c.2 This surveillance requires that a representative carbon sample be obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978 and that a laboratory analysis verify that the representative :arbon sample meets the laboratory testing criteria of ASTM D3803-89 and Millstone Unit 3 specific parameters.

The laboratory analysis is requirod to be p-rformed within 31 days after removal of the sample.

ANSI N510-1980 is used in lieu of ANSI N510-1975 referenced in Revision 2 of Regulatory Guide 1.52.

4.7.7.c.3 This surveillance verifies that a system flow rate of 1,120 cfm +/- 20%,

during system operation when testing in accordance with ANSI N510-1980.

4.7.7.d After 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation, a representative carbon sample must be obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, and a laboratory analysis must verify that the representative carbon sample meets the laboratory testing criteria of ASTM D3803-89 and Millstone Unit 3 specific parameters.

MILLSTONE

- UNIT 3 B 3/4 7-14 Amendment No.

7 0 U, 206 0867

PLANT SYSTEMS BASES 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM (Continued)

SURVEILLANCE REOUIREMENTS (Continued).

The laboratory analysis is required to be performed within 31 days after removal of the sample.

ANSI N510-1980 is used in lieu of ANSI N510-1975 referenced in Revision 2 of Regulatory Guide 1.52.

The maximum surveillance interval is 900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, per Surveillance Requirement 4.0.2.

The 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of operation requirement originates from Nuclear Regulatory Guide 1.52, Table 2, Note C. This testing ensures that the charcoal adsorbency capacity has not degraded below acceptable limits as well as providing trending data.

4.7.7.e.l1 This surveillance verifies that the pressure drop across the combined HEPA filters and charcoal adsorbers banks at less than 6.75 inches water gauge when the system is operated at a flow rate of 1,120 cfm +/- 20%.

The frequency is at least once per 24 months.

4.7.7.e.2 This surveillance verifies that the system maintains the control room at a positive pressure of greater than or equal to 1/8 inch water gauge at less than or equal to a pressurization flow of 230 cfm relative to adjacent areas and outside atmosphere during positive pressure system operation.

The frequency is at least once per 24 months.

The intent of this surveillance is to verify the ability of the control room emergency air filtration system to maintain a positive pressure while running in the filtered pressurization mode.

MILLSTONE - UNIT 3 0934 B 3/4 7-15 Amendment No. X1f, JFX, 00, XP; 206 I

PLANT SYSTEMS BASES 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM (Continued)

SURVEILLANCE REQUIREMENTS (Continued)

During the first hour, the control room pressurization system creates and maintains the positive pressure in the control room.

This capability is verified by Surveillance Requirement 4.7.8.C, independent of Surveillance Requirement 4.7.7.e.2.

A CBI signal will automatically align an operating filtration system into the recirculation mode of operation due to the isolation of the air supply line to the filter.

After the first hour of an event with the potential for a radiological release, the control room emergency ventilation system will be aligned in either the recirculation mode (isolated from the outside environment) or filtered pressurization mode (outside air is diverted through the filters to the control room envelope to maintain a positive pressure).

The mode of service for the control room emergency air filtration system will be based on the radiological conditions that exist outside the control room.

Alignment to the filtered pressurization mode requires manual operator action to open the air supply line.

4.7.7.e.3 This surveillance verifies that the heaters can dissipate 9.4 +/- I kW at 480V when tested in accordance with ANSI N510-1980.

The frequency is at least once per 24 months.

The heater kW measured must be corrected to its nameplate rating.

Variations in system voltage can lead to measurements of kW which cannot be compared to the nameplate rating because the output kW is proportional to the square of the voltage.

4.7.7.f Following the complete or partial replacement of a HEPA filter bank, the operability of the cleanup system should be confirmed.

This is accomplished by verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criterion of less than 0.05% in accordance with ANSI N510-1980 for a DOP test aerosol while operating the system at a flow rate of 1,120 cfm +/- 20%.

MILLSTONE - UNIT 3 B 3/4 7-16 Amendment No.

206 0934

PLANT SYSTEMS BASES 3/4.7.8 CONTROL ROOM ENVELOPE PRESSURIZATION SYSTEM (Continued)

SURVEILLANCE REQUIREMENTS (Continued) 4.7.8.c The performance of the control room envelope pressurization system should be checked periodically.

The frequency is at least once per 24 months and following any major alteration of the control room envelope pressure boundary.

A major alteration is a change to the control room envelope pressure boundary that:

(1) results in a breach greater than analyzed for acceptable pressurization and requires nonroutine work evolutions to restore the boundary.

A nonroutine work evolution is one which makes it difficult to determine As-Found and As-Left conditions.

Examples of routine work evolution include:

(1) opening and closing a door, and (2) repairing cable and pipe penetrations because the repairs are conducted in accordance with procedures and are verified via inspections.

For these two examples, there is a high level of assurance that the boundary is restored to the As-Found condition.

This surveillance requires at least once per 24 months or following a major alteration of the control room envelope pressure boundary by:

Verifying the control room envelope is isolated in response to a Control Building Isolation Test signal, Verifying, after a 60 second time delay following a Control Building Isolation Test signal, the control room envelope pressurizes to greater than or equal to 0.125 inch water gauge relative to adjacent areas and outside atmosphere; and Verifying the positive pressure of Technical Specification 4.7.8.c.2 is maintained for greater than or equal to 60 minutes.

Changes in conditions outside the control room envelope cause pressure spikes which are reflected on the differential pressure indicator, 3HVC-PDI 113.

Pressure spikes or fluctuations which result in the differential pressure momentarily dropped below the 0.125 inch water gauge acceptance criteria are acceptable providing the following conditions are met:

1.

Differential pressure remains positive at all times.

2.

Differential pressure is only transitorily below the acceptance criteria.

3.

Differential pressure returns to a value above the acceptance criteria.

Amendment No. 7JF, IF;,

206 MILLSTONE - UNIT 3 0935 B 3/4 7-21