Text

Amend 72 to License DPR-65,changing Tech Specs Re Mode 6 Reactivity Control,Boration Requirements & Special Test Peak Linear Heat Rate
	ML20041D017
Person / Time
Site:	Millstone
Issue date:	02/22/1982
From:	Clark R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20041D018	List: ML20041D017; ML20041D019; ML20041D021;
References
	TAC-47471, TAC-47472, NUDOCS 8203040069
	Download: ML20041D017 (59)
	v • d • e

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!S NUCLEAR REGULATORY COMMISSION

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%.. s NORTHEAST NUCLEAR ENERGY COMPANY THE C0tmECTICUT LIGHT AND POWER COMPANY THE HARTFORD ELECTRIC LIGHT COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 72 License No. OPR-65 1.

The Nuclear Regulatory Commission (the Commission).has found.that:

A.

The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated December 17, 1981, complies with the standards and requirements of the Atomic Energy ",ct i 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; S.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulaticns of the Ccmmission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security cr to the health and safety of the public; I

and E.

The issuance of this amendment is in acccrdance with 10 CFR Part.

., s 51 of the Commissien's regulations and all a:plicable recuirements i

have been satisfied.

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PDR ADOCK 05000336 P

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No OPR-65 is hereby a-ar.ded to read as follows:

(2) Technical Soecifications The Technical Specifications contained in A;pendices

^

A and B, as revised through Amendment No. 72, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This licanse amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION ob Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specificatiens Date of Issuance:

February 22, 1982 e

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s ATTACHMENT TO LICENSE AMENDMENT NO. 72 FACILITY OPERATING LICENSE NO. DPR -

DOCKET NO. 50-336

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Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified-by Amendment number and contain vertical lines. indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Pages V

X 3/4 7-16 1-7 3/4 7-17 3/4 1-1 3/4 '-18

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3/4 1-3 3/4 9-1 3/4 1-16 3/4 9-16 3/4 2-3 3/4 9-17 3/4 3-1 3/4 9-18 3/4'3-4 3/4 10-1 3/4 3-12 B 3/4 1-3 3/4 3-14 B 3/4 4-12 3/4 3-18 B 3/4 5-1 3/4 3-19 B 3/4 6-2 3/4 3-20 B 3/4 9-1 3/4 3-24 3/4 4-23 3/4 4-24 3/4 6-25 3/4 6-26 3/4 6-27

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LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4.4 PRESSURIZER..........................................

3/4 4-4 3/4.4.5 STEAM GENERATORS.....................................

3/4 4-5 3/4.4.6.

REACTOR COOLANT SYSTEM LEAKAGE........'...............

3/4 4-8 Lea kage Detection Sys tems............................

3/4 4-8 Reactor Coolant System Leakage.......................

3/4 4-9 3/4.4.7 CHEMISTRY............................................

3/4 4-10 3/4.4.8 SPECIFIC ACTIVITY....................................

3/4 4-13 3/4.4.9 PRESSURE /TEMhERATURE LIMITS..........................

3/4 4-17 Reactor Cool ant Sys tem...............................

3/4 4-17 Pressurizer..........................................

3/4 4-21 Overpressure Protection Systems......................

3/4 4-21a 3/4.4.10 STRUCTU RAL INTEGRITY.................................

3/4 4-22 1

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANKS........................,.......

3/4 5-1 3/4.5.2.ECCS SUBLYSTEMS - T,yg >.300 F.......................

3/4 5-3 3/4.5.3 EC.CS SUBSYSTEMS - T,yg < 300"F.......................

3/4 5-7 s 3/4.5.4 REFUELING WATER STCRAGE TANK.........................

3/4 5-8 MILLSTONE - UNIT 2 V

Amendment No. 86 7 2 i

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.*m.=e INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT..................................

3/4 6-1 Containment Integrity................................

3/4 6-1

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Containment Leakage..'........'.'....'...................

3/4 6-2

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Co nta i nme n t Ai r Lo cks................................

3/4 6-6 Internal Pressure....................................

3/4 6-8

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3/4 6-9 Ai r, Te mp e ra t u re......................................

1 Containment Structural Integri ty.....................

3/4 6.0 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS.................

3/4 6-12 Contai nment Spray System.............................

3/4 6-12 Containment Ai r Reci rculation System.................

3/4 6-14 3/4.6.3 CONTAINMENT ISOLATION VALVES.........................

3/4 6-15 3/4.6.4 COMBUSTIBLE GAS CONTR0L..............................

3/4 6-20 Hy d ro g e n A n al y z e rs...................................

3/4 6-20 Electric Hydrogen Recombiners - W...................

3/4 6-21 Hydrogen Purge System................................

3/4 6-23 Post-Incident Reci rculation Systems..................

3/4 6-24 3/4.6.5 SECONDARY CONTAINMENT................................

3/4 6-25 Encl osure Building Filtration System.................

3/4 6-25 Enclosure Building Integrity.........................

3/4 6-28 Oh MILLSTONE - UNIT 2 VI-

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INDEX BASES PAGE SECTION 3/4.0 APPLICABILITY..........................................

B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS,

3/4.1.1 30 RATION CONTR0L.....................................

B 3/4 1-1 3/4.1.2 B0 RATION SYSTEMS.....................................

B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES...........................

B 3/4 1-3

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3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE.....................................

BJ3/4 2-1 T

B 3/4 2-1 3/4.2.2 T0TAL PLANAR RADIAL PEAKING FACTOR - Fxy.............

3/4.2.3 TOTALINTEGRATEDRADIALPEAKINGFACTOR-Ff...........B3/42-1 3/4.2.4 AZIMUTHAL POWER TILT.................................

B 3/4 2-1 1

3/4.2.5 FUEL RESIDENCE TIME..................................

B'3/4 2-2 3/4.2.6 DNB MARGIN.......................................... B 3/4 2-2 3/4.3 INSTRUMENTATION 3/4.3.1 PROTECTIVE INSTRUMENTATION...........................

B 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE INSTRUMENTATION............

B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION...........................

B 3/4 3-2 s.

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MILLSTONE - UNIT 2

, IX Amendment No. 38,49

INDEX BASES SECTION PAGE 3/4.4 REACTOR COOLANT' SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION.................... B 3/4 4-1 3/4.4.2 S AFETY VALV ES........................................... B 3/ 4 4-1 3/4.4.3 R EL I E F V ALV ES........................................... B 3/4 4-2

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3/4.4.4 PR ES S U R I ZER............................................. B 3/ 4 4-2 3/4.4.5 STEAM GENERATORS........................................ B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE.......................... B 3/4 4-3 3/4.4.7 CHEMISTRY............................................... B 3/4 4-4 3/4.4.8 SPECIFIC ACTIVITY....................................... B 3/4 4-4 3/4.4.9 PRESSURE / TEMPERATURE ' LIMITS............................. B 3/4 4-5 3/4.4.10 STRUCTURAL INTEGRITY.................................... B 3/4 4-11 l

l 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANKS.................................. B"3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS.............................. B 3/4 5-1 3/4.5.4-REFUELIN3 WATER STORAGE TANK (RWST)..................... B 3/4 5-2 s.

.s MILLSTONE - UNIT 2 X

Amendment No. & S, 7 2

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TABLE 1.'l OPERATIONAL MODES REACTIVITY

% RATED AVERAGE COOLANT MODE CONDITION, K THERMAL POWER

TEMPERATURE ff

> 0.99

> 5%

> 300*F l

1.

POWER OPERATION

0. 99..

_... - < 5%

> 300*F 2.

STARTUP 3.

HOT STANDBY

< 0.99 0

> 300 F 4.

HOT SHUTDOWN

< 0.99 0

300*F> T 1

avg l

> 200*F 5.

COLD SHUTDOWN

< 0.98 0

1 200 F 6.

REFUELING **

< 0.95 0

L 140*F

Excluding decay heat.

Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

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-s MILLSTONE - UNIT 2 1-7 Amendment No. H,7 2 e

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TABLE 1.2 FREQUENCY NOTATION NOTATION FRE00EF,Y

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S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l W

At least once'per'7 days.

M At least once per 31 days.

Q At least once per 92 days.

2

.SA At least once per 6 months.

R At least once per 18 months.

Prior to each reactor startup.

S/U i

N.A.

Not applicable.

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3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - T,yg > 200*F LIMITING CONDITION FOR OPERATION l

3.1.1.1 The SHUTDOWN MARGIN shal.1_be 1 3.20% ak/k.

APPLICABILITY: MODES 1, 2*, 3 and 4.

ACTION:

With the SHUTOOWN MARGIN' <.3.20% ak/k, within 15 minutes initiate and

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continue boration at 1 40 gpm of boric acid solution at or great'er than the required refueling water storage tank (RWST) concentration (ppm) until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE RE0VIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be 1 3.20% ak/k:

a.

Immediately upon detection of an inoperable CEA.

If the inoperable CEA is immovable or untrippable, the SHUTDOWN MARGIN, required by Spe~cification 3.1.1.1, shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable CEA.

b.

When in MODES 1 or 2, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that CEA group withdrawal is within the Transient Insertion Limits of. Specification 3.1.3.6.

c.

Prior to initial operation above 5% RATED THERMAL POWER af ter each refueling, with the CEA groups at the Transient Insertion Limits of Specification 3.1.3.6.

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See Special Test Exception 3.10.1.

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MILLSTONE - UNIT 2 3/4 1-1 Amendment Mo. ?S', py,7 2 a

REACTIVITY CONTROL SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) d.

When in MODES 3 or 4, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consider-ation of the following factors:

1.

Reactor coolant system boron concentration, 2.

CEA position, 3.

Reactor coolant temperature, 4.

Fuel burnup based on. gross, therm.a.1 energy generation, 5.

Xenon concentration, and 6.

Samarium concentration.

4.1.1.1.2 The overall core reactivity balance shall be compared to predicted values to demonstrate agreement within + 1.0% ak/k at least once per 31' Effective Full Power Days. This comparison shall consider at least those factors stated in Specification 4.1.1.1.1.d, above. The predicted reactivity values shall be adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 Effective Full Power Days after each refueling.

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REACTIVITY CONTROL SYSTEMS SHUTOOWN MARGIN - T,yg < 200*F LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be 3,2.0% ak/k.

APPLICABILITY: MODE 5.

ACTION:

With the SHUTDOWN MARGIN < 2.0% ak/k, within 15 minutes initiate and continue boration at 3,40 gpm of boric acid solution at or greater than the required refueling water storage tank (RWST) concentration (ppm) until the required' SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.2 The SHUTDOWN MARGIN shall be determined to be 3,2.0% ak/k:

a.

Immediately upon detection of an inoperable CEA.

If the inoperable CEA is immovable or untrippable, the SHUTDOWN MARGIN required by Specification 3.1.1.2 shall be increased by an amount at least equal to the withdrawn worth of the inmovable or untrippable CEA.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the followir.3 factors:

1.

Reactor coolant system boron concentration, 2.

CEA position,,

3.

Reactor coolant temperature, 4

Fuel burnup based on gross thermal energy generation, 5.

Xenon concentration, and 6.

Samarium concentration.

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MILLSTONE - UNIT 2 3/4 1-3 Amendment No.61, 7 2 l

REACTIVITY CONTROL SYSTEMS BORON DILUTION LIMITING CONDITION FOR OPERATION

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The flow rate of reactor coolant through the core shall be 3.1.1.3

> 3000 gpm whenever a reduction in Reactor Coolant System boron concentation is being made.

APPLICABILITY: ALL MODES.

ACTION _:

With the flow rate of reactor coolant through the core < 3'000 gpm, immediately suspend all operations involving a reduction in boron concentration of the Reactor Coolant System.

SURVEILLANCE REQUIREMENTS The reactor coolant flow rate through the core shall be 4.1.1.3 determined to be > 3000 gpm prior to the start of and at least once per hour during a reduction in the Reactor Coolant System boron

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concentration by either:

Verifying at le'ast one reactor coolant pump is in operation, a.

or Verifying that at least one low pressure safety injection pump b.

is in operation and supplying > 3000 gpm through the core.

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j REACTIVITY CONTROL SYSTEMS BORIC ACID PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 1

The boric acid pump (s) in the boron injection flow path (s) required OPERABLE pursuant to Specification 3.1.2.2a shall be OPERABLE 3.1.2.6 if the flow path through the boric acid pump in Specification 3.1.2.2a l'

is OPERABLE.

i APPLICABILITY: MODES 1, 2, 3 and 4.

I ACTION:

tlith one boric acid pump required for the boron injection flow path (s) pursuant to Specification 3.1.2.2a inoperable, restor the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

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SURVEILLANCE REQUIREMENTS T

The boric acid pump (s) shall be demonstrated OPERABLE at least 4.1.2.6 once per 7 days by:

Starting (unless already operating) the pump from the control "a.

room, Verifying, that on recirculation flow, the pump develops a b.

discharge pressure of > 98 psig, and I

Verifying pump operation for at least 15 minutes.

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REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - SHUTDOWN 1

LIMITING CONDITION FOR OPERATION 3.1.2.7 As a minimum, one of the following borated water sources shall be OPERABLE:

One boric acid storage tank and one associated heat tracing a.

circuit with the tank contents in accordance with Figure 3.1-1.

b.

The refueling water storage tank with:*

I 1.

A minimum contained volume of 57,000 gallons, 2.

A minimum boron concentration of 1720 ppm when in Mode 5,

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3.

A minimum boron concentration as defined in Specification 3.9.1 when in Mode 6.

4.

A minimum solution temperature of 35'F.

I APPLICABILITY: MODES 5 and 6.

ACTION:

With no barated water sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until at least one borated water source is restored to OPERABLE status.

SURVEILLANCE REQUIREMENTS 4.1.2.7 The above required borated water source shall be demonstrated OPERABLE:

At least once per 7 days by:

a.

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Verifying the boron concentration of the water, s,

2.

Verifying the water level of the tank, and 3.

V6rifying the boric acid storage tank solution temper -'

ature when it is the source of borated water.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature when it is the :curce of borated water and the RWST ambient air temperature is < 35'F.

MILLSTONE - UNIT 2 3/4 1-16 Amendment No. 77,y

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i 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION LIMITING CONDITION FOR OPERATION i

3.3.1.1 As a minimum, the reactor protective instrumentation channels and j

bypasses of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in j

Table 3.3-2.

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APPLICABILITY: As shown in Table 3.3-1.

ACTION:

l As shown in.. Table 3.3-1..

SURVEILLANCE REQUIREMENTS 4.3.1.1.1 Each reactor protective instrumentation channel shall be demonscrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATICH and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in Table 4.3-1.

4. 3.1.1. 2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation. The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by bypass operation.

4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months.

Each test shall include at least one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1.

4.3.1.1.4 The response time of all REACTOR TRIP SYSTEM resistance temperature

'i detectors (RTD) shall be verified to be less than or equal to the value w

specified in Table 3.3-2 within one month of operation for newly installed

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RTD's and once every 18 months thereaf ter.

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TABLE 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION 2

7-MINIMUM 0;

TOTAL NO.

CHANNELS CHANNEL 5 APPLICABLE g-M FUtiCTIONAL UNIT OF CilANNELS_

TO TRIP OPERABL:

MODES ACTION 1.

Manual Reactor Trip 2

1 2

1, 2 and

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2.

Power Level - High 4

2 (f) 3 1, 2 2

m 3.

Reactor Coolant Flow - Low 4

2(a) 3 1, 2 (e) 2 l.

4.

Pressurizer Pressure - liigh 4

2 3

1, 2 2

5.

Containment Pressure - liigh 4

2 3

2 6.

Steam Generator Pressure - Low 4 2(b) 3 1,' 2 2

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Steam Generator Water 1, 2 2

Level - Low 4

2 3

8.

Local Power Density - liigh 4

2(c) 3' 1

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9.

Thennal Margin / Low Pressure 4

2(a) 3 1, 2 (e) 2

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10. Loss of Turbine--Ilydraulic R

Fluid Pressure - Low 4

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I TABLE 3.3-1 (Continued) 3 REACTOR PROTECTIVE IllSTRUMEtiTATI0tt F

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TOTAL t10.

CHAlitlELS CilAtillELS APPLICABLE FUtiCTI0tiAL UtilT.

OF CHAtiNELS TO TRIP OPERABLE MODES ACTION m

cy

11. Wide _ Range Logaritiunic fleutron

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Flux Monitor - Shutdown 4

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12. Underspeed - Reactor Coolant Pumps I

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TABLE 3.3-1 (Continued)

TABLE NOTATION With the protective system trip breakers in the closed position and the CEA drive system capable of CEA withdrawal.

(a) Trip may be bypassed below 5% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is 2, 5% of RATED THERMAL POWER.

(b) Tripmaybemanuallybypassedb'el'ow605p'ia;bypassshallbe s

automatically removed at or above 600 psia.

(c) Trip may be bypassed below 15% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is > 15% of

-RATEU' THERMAL POWER.

(d) Deleted.

(e) Trip may be bypas. sed during testing pursuant to Special Test.Excep -

tion 3.10.3.

(f) AT Power input to trip may be bypassed below 5% of RA,TED THERMAL POWER; bypass shall be automatically removed when THE N L POWER 15 3,3% of RATED THERMAL POWER.

ACTION STATEMENTS ACTION 1 With the number of channels OPERABLE one less than required by the Minimum Channels GPERABLE requirement, restore the inoperable channel to OPERABLE s'tatus within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and/or open the protective system trip breakers.

With the number of OPERABLE channels one less than the ACTION 2 Total Number of Channels and with the THERMAL POWER level:

< 5% of RATED THERMAL POWER, immediately place the a.

Inoperable channel in the bypassed condition; restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 5% of RATED THERMAL s.

-s POWER.

b.

> 5% of RATED THERMAL POWER, operation may continue with the inoperable channel in the bypassed condi,

tion, provided the following conditions are satisfied:

MILLSTONE - UNIT 2 3/4 3-4 Amendment No. 9, 7$,7 2 w w w

a.-,s e

e.s

p-%

-=t*

e--*

g

\\

INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Continued) i i

~

The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESF 4.3.2.1.3 function shall be demonstrated to be within the limit at least once per Each test shall include at least one channel per function 18 months.

such that all channels are tested at least once every N times 18 months where H is the total number of redundant channels in a specific ESF function as shown in the " Total.No.,of,Chan.nels" Column of Table 3.3-3.

The trip value shall be such that the containment purge 4.3.2.1.4 effluent shall not result in calculated concentrations of radioactivity j

offsite in excess of 10 CFR Part 20, Appendix B, Table II.6 Forgheshall purposes of calculating this trip value, a x/Q = 5.8 x 10 sec/m t

andaX/Q=7.5x10-gmisa}ignedtopurgethroughthebuildingvensha be used when the syst sec/m to purge through the Unit i stack, the gaseous and aprticulate (Half Lives greater than 8 days) radioactivity shall be asusmed to be Xe-133 and Cs-137,5respectively. However, the setpoints shall be no greater than 5 x 10 cpm.

e l

1 Ok 4

9 MILLSTONE - UNIT 2 3/4 3-11 Amendment No. 49

i t

TABLE 3.3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM. INSTRUMENTATION ~

=

MINIMUM m

TOTAL NO.

CilANNELS CHANNELS APPLICABLE OPERABLE MODES ACTION FUNCTIONAL UNIT OF CilANNELS TO TRIP E

p 1.

. SAFETY IllJECTION (SIAS) e a.

Manual (Trip Buttons) 2 1

2 1,2,3,4 1

J, m

b.

Containment Pressure -

liigh 4

2 3

1,2,3 2

l c.

Pressurizer Pressure -

1,2(e),3(a) 2 l

Low 4

2 3

2.

CONTAINMENT SPRAY (CSAS) a.

Manual (Trip Buttons) 2 1

2 1, 2, 3, 4 1

l m

i g

b.

Containment Pressure --

wi liigh - liigh 4

2(b) 3 1,2,3 2

l m

3.

CONTAINMENT ISOLATION (CIAS) a.

Manual CIAS (Trip l

Buttons) 2 1

2 1,2,3,4 1

I i

h"g b.

Manual SIAS (Trip

!}

Buttons) 2 1

2 1,2,3,4 1

l i

c.

Containment Pressure -

g liigh 4

2 3

1,2,3 2

l

~

d.

Pressurizer Pressure -

~

Low 4

2 3

1,2(e),3(a) 2 l

p t

,f

)

~

o TABLE 3.3-3 (Continuedl

~

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION x

^

E MINIMUM l

C TOTAL NP.

CilANNELS CllANNELS APPLICABLE y

FUNCTIONAL UNIT' 0F CilANNELS TO TRIP OPERABLE MODES ACTION m

4.

MAIN STEAM LINE c-ISOLATION Steam Generator 4

2 3

1,2,3(c)-

2 l

Pressure - Low 5.

ENCLOSURE BUILDING FILTRATION (EBFAS)

~

a.

Mantal E AS (Trip 2

1 2-1,2,3,4 1

l b.

Manual SIAS (Trip Buttons) 2 1

2 1,2,3,4

~1 l

s c.

Containment Pressure -

I liigh 4

2 3

1, 2, 3 2

l

[

d.

Pressurizer Pressure -

Low 4

2 3

1,2,3(a) 2 l

l 6.

CONTAINMENT SUMP ~

RECIRCULATION (SRAS) a.

Manual SRAS (Trip k

Buttons) 2 1

.2 1,2,3,4 1

I a

I.*

[

b.

Refueling Water Storage Tank - Low 4

2 3

1, 2, 3 2

g I

g h

O

.J

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION x

E MINIMUM EE TOTAL NO.

CilANNELS CHANNELS APPLICABLE cs FUNCTIONAL UNIT OF CilANNELS TO TRIP

,'0PERABLE MODES ACTION

$5 e

7.

CONTAINMENT PURGE c:

VALVE ISOLATION "L

'd Containment Radiation -

a.

liigh 5, 6 l

Gaseous Monitor-

'1(d) 1(d) 1 3

Particulate Monitor 1(d) 1(d) 1 3

8.

LOSS OF POWER w

1 a.

4.16 kv Emergency Bus Undervoltage (Under-u, voltage relays) -

1evel one 4/ bus 2/ Bus 3/ bus 1, 2, 3 2

)

b.

4.16 kv Emergency Bus Undervoltage (Under-voltage relays) -

level. two 4/ Bus 2/ Bus 3/ Bus 1, 2, 3 2

li

~

a ht a

j l

EI f5 ma i

to I

.e e

I g

TABLE 3.3-3 (Continued) l l

ACTION 3 With one or more channels inoperable, operation may continue {

i, provided the containment purge valves are maintained closed.

s.

-s MILLSTONE - UNIT 2 3/4 3-17 Amendment f:o. A6 63

t t

TABLE 3.3-4 2_.

ENGINEERED SAFETY FEATliRE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES

{$

z" ALLOWABLE

[

FUNCTIONAL UNIT '

TRIP SETPOINT VALUES z

U l.

SAFETY INJECTION (SIAS) m a.

Manual (Trip Buttons)

Not Applicable Not Applicable b.

Containment Pressure - liigh 1 4.75 psig 1 5.20 psig' I

I Pressurizer Pressure - Low 1 1600 psia 1 1592.5 psia l

~

c.

2.

CONTAINMENT SPRAY (CSAS) a.

Manual (Trip Buttons)

Not Applicable Not Applicable t

g.

b.

Containment Pressure -- liigh-liigh 1 27 psi 9

1 27.45 psig l

u

)

y.

3.

CONTAINMENT ISOLATION (CIAS) g a.

Manual CIAS (Trip Buttons)

Not Applicable Not Applicable llj b.

Manual SIAS (Trip Buttons)

Not Applicable Not Applicable u

]

c.

Containment Pressure - liigh 1 4.75 psig 1 5.20 psig l

y d.

Pressurizer Pressure - Low 1 1600 psia 1 1592.5 psia l

5' 4.

MAIN STEAM LINE ISOLATION l

Steam Generator Pressure - Low 1 500 psia 1 492.5 psla l

2 n

I' i

I S

.a

s t

TABLE 3.3-4 (Continued) 25 17 ENGINEERED SAFETY FEATURE Ac.TUATION SYSTEM INSTRUMENTATION TRIP VALUES E2

=

ALLOWABLE l_

FUNCTIONAL UNIT TRIP VALUE VALUES 5.

ENCLOSURE BUILDING FILTRATION (EBFAS)

Manual EBFAS (Trip Buttons)

Not $pplicable Not Applicable a.

b.

Manual SIAS (Trip Buttons)

Not Applicable Not Applica' ole

~

c.

Containment Pressure - liigh 1 4.75 psig 1 5.20 psig d.

Pressurizer Pressure - Low

> 1600 psia

> 1592.5 psia 6.

CONTAINMENT SUMP RECIRCULATION (SRAS)~

a.

Manual SRAS (Trip Buttons)

Not Applicable Not Applicable h{.

b.

Refueling Water Storage Tank - Low 48 + 9 inches above 48 + 18 inches above

,l tank bottom tank bottom e

G$ "

^

7.

00flTAINMENT PURGE VALVES ISOLATION a.

Containment Radia tion - liigh Gaseous Activity

< the value determined

< the value determined in accordance with in accordance with 2r Speci fica tion 4.3.2.1.4.

Speci fication 4.3.2.j.q.

m h

Particulate Activity (llalf 1 the value detenaltied 1'the value determined' g

Lives greater than 8 days) in accordance with

.in accordance with Spec'i fica tion 4.3.2.1.4.

Speci fication 4.3.2.1.4.

r+

5 t

Z$

s

,a P..a b

I TABLE 3.3-4 (Continued) x

~

G ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES r-8 M

ALLOWABLE FUNCTIONAL UNIT TRIP VALUE VALUES e

c-2 z

U 8.

LOSS OF POWER i

~

a.

4.16 kv '.1ergency Bus Undervoltage (Undervoltage relays) - level one

> 2912 volts

> 2877 volts

> 3663 volts with I

b.

4.16 kv L,ergency Bus Undervoltage

> 3700 volts with an 8.0 + 2.0 second (Undervolttge relays) - level two an 8.0 + 2.0 second

.~

time deTay time deTay 9.

AUXILIARY FEEDWA1ER

~

R a.

Manual Not Applicable Not Applicable u

b.

Steam Generator Level - Low

> 12%

> 10%

h!

I

=

eh

-a R

l'

.O f

a

?:

3 N

m O-

I TABLE 4.3-2 h

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS v,

d CilANNEL MODES IN WHICH

.M CilANNEL CilANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT -

CllECK CALIBRATION -

TEST REQUIRED C

=_i 1.

SAFETY INJECTION (SIAS) a.

Manual (Trip Buttons)

N.A.

R N.A.

H b.

Containment Pressure - liigh S

R M

1,2,3 c.

Pressurizer Pressure - Low S

R' M

1,2,3 d.

Autonatic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3 2.

C0"TAINMENT SPRAY (CSAS)

N.A.

a.

Manual (Trip Buttons)

N.A.

R b.

Containment Pressure --

liigh - High S

R M

1, 2, 3 c.

Automatic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3 3.

CONTAINMENT ISOLATION (CIAS)

Y a.

Manual CIAS (Trip Buttons)

N.A.

R N.A.

E!

b.

Manual SIAS (Trip Buttons)

N.A.

R N.A.

c.

Containment Pressure - iligh S

R M

1, 2, 3 d.

Pressurizer Pressure - Low S

R M.

1,2,3 e.

Automatic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3 4.

MAIN STEAM LINE ISOLATION a.

Steam Generator Pressure - Low S R

H 1, 2, 3 b.

Auto.natic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3 5.

ENCLOSURE BUILDING FILTRATION (EBFAS) a.

Manual E8FAS (Trip Buttons)

N.A.

R N.A.

b.

Manual SIAS (Trip Buttons)

N.A.

R N.A.

c.

Containment Pressure - High S

R M

1, 2, 3 d.. ' Pressurizer Pressure - Low S

R M

1,2,3 e.

Automatic Actuation Logic N.A.

N.A.

M(1 )

1, 2, 3

./

g P'

e

~

TABLE 4.3-2 (Continued) x_

~

h ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WilICH M

CilANNEL CilANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CllECK CALIBRATION' TEST REQUIRED __

c

_z 6.

CONTAINMENT SUMP RECIRCULATION (SRAS) a.

Manual SRAS (Trip Buttons)

N.A.

R N.A.

1 b.

Refueling Water Storage i

Tank - Low S

R M

1, 2, 3 c.

Automatic Actuation Logic N.A.

N.A.

M(1) 1, 2, 3 7.

CONTAINMENT PURGE VALVES ISOLATION i

f R

a.

Containment Radiation - liigh Gaseous Monitor S

R M,

ALL MODES ALL MODES y

Particulate Monitor S

R H,

's

~.

8.

LOSS OF POWER a.

4.16 kv Emergency Bus Undervoltage (Undervoltage relays) - level one S

R M

1, 2, 3 b.

4.16 kv Emergency Bus E

Undervoltage (Undervoltage g

relays) - level two S

R M

1, 2, 3 R

9.

AUXILIARY FEEDWATER.

a.

Manual N.A.

N.A.

R N.A.

h P

b.

Steam Generator Level - Low 5

R H

1, 2, 3 8

to

(

3 p

)

t This page intentionally lef t blank s.

- s t

MILLSTONE - UNIT 2 3/4 4-23 Amendment No. 70, 77

~

f This page intentionally left blank c

-s MILLSTONE - UNIT 2 3/4 4-24 Amendment No. 70, y7

,----mmer,___

-e m-ew -

m %-, a w =

-*-- = =.**

m.... J ~,.. - _, _.

CONTAINMENT SYSTEMS 4

3/4.6.5 SECONDARY CONTAINMENT ENCLOSURE BUILDING FILTRATION SYSTEM

~

LIMITING CONDITION FOR OPERATION 3.6.5.1 Two separate and independent enclosure building filtration systems shall be.0PERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one. enclosure building filtration system inoperable,. restore the inoperable system to OPERABLE status within 7 days or be in COLD SHUT-DOWN within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

SURVEILLANCE RFQUIREMENTS 4.6.5.1 Each enclosure building filtration system shall be demonstrated OPERABLE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by initia.t-ing, from the control room, flow through the HEPA filter and charcoal adscrber train and verifying that the train operates for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heaters on.

b.

At least once per 18 months or (1) af ter 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:

kS O

O s

e MILLSTONE - UNIT 2 3/4 6-25 A'mendment No. 7 g e

~

CONTAINMENT SYSTEMS _

! SURVEILLANCE REQUIREMENTS (Continued)

'[

1.

Verifying that the cleanup system satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.S.a. C.5.c ar.d C.5.d of Regulatory Guide 1.52, Revision 2 March 1978, and the system flow rate is 9000 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, meets the. laboratory-testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.

3.

Verifying a system flow rate of 9000 cfm + 10% during system operation when tested in accordance with ANSI N510-1975.

'hfter every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying

~

'c.

within 31 days af ter removal that a laboratory analysis of a.representa-tive carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52 Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Re'gulatory Guide 1.52, Revision 2. March 1978.

d.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is < 6 inches Water Gauge while operating the system at a flow rate of 9000 cfm f;10%.

2.

Verifying that the system starts on an Enclosure Building Filtra-tion Actuation Signal (EBFAS).

3.

Verifying that each system produces a negar,ive pressure of greater than or equal to 0.25 inces W.G. in the Enclosure Building Filtration Region within (1) minute after an EBFAS.

s Af ter each complete or partial replacement of a HEPA filter bank by e.

verifying that the HEPA filter banks remove greater than or equal to 99% of the 00P wi.en they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 9000 cfm i

f; 10%.

3 s.

MILLSTONE - UNIT.2 3/4 6-26 Amendment No. 25, 7 n e

'- -i- __

_h+y pg.._%%

,,q,_,

I CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) f.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 9000 cfm + 10%.

C w

-)

MILLSTONE - UNIT 2 3/4 6-27 Amendment No. 7 2 e

.~1 i

t CONTAINMENT SYSTEMS '

ENCLOSURE BUILDING INTEGRITY LIMITING CONDITION FOR OPERA' TION 9

3.6.5.2 ENCLOSURE BUILDING INTEGRITY shall be maintained.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

Without ENCLOSURE BUILDING INTEGRITY, restore ENCLOSURE BUILDING INTEGRITi within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in COLD SHUTDOWN within the next 36 bcurs.

SURVEILLANCE REQUIREMENTS 4.6.5.2 ENCLOSURE BUILDING INTEGRITY shall be demonstrated at least I

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.

s.

.s

~

MILLSTONE - UNIT 2 3/4 6-28 '

Amendment No. 25, 45 l

m... m m - -

..m

1 b,

L w

E

~

l d

b

't y

~n

't%

bm\\

5 s s q

u Y

v

?x g

a8

=

N NM

~

s

-s e

Critical Area Figure 3.7-1 MILLSTONE - UNIT 2 3/4 7-15 A-

3 t

a.

e PLANT SYSTEMS 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM

~

LIMITING CONDITION FOR OPERATION 3.7.6.1 Two independent control room emergency ventilation systems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one control room emergency ventilation system inoperable, restore the system to OPERABLE status within 7 days or be in COLD SHUT 00WN within'the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ; SURVEILLANCE REOUIREMENTS 4.7.6.1 Each control room emergency ventilation system shall be demon-strated OPERABLE:

At least-once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the control room a.

air temperature is $_120*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 absorber train and verifying that the system operates for at least 15 minutes.

e At least once per 18 months or (1) after any structural maintenance

c.

on the HEPA filter or charcoal adsorber housings., or (2) followteg --

ptinting, fire or chemical release in any ventilation zone i-communicating with the system by:

No J

MILLSTONE - UNI 2 3/4 7-16 Amendment No. 7 2 t.

- nn-r s., n.

n._

PLANT SYSTEMS SURVEILLANCEREQUIREMENTS(Continued) 1.

Verifying that the cleanup system satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5.a. C.S.c and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 2000 cfm f;

^

10%.

l 2.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position'C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52 Revision 2, March 1978.

3.

Verifying a system flow rate of 2000 cfm + 10% during system

~

, operation when tested in accordance with ANSI N510-1975.

d.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying within 31 days af ter removal that a laboratory analysis of a represen-tative carbon sample obtained in accordance with Regulatory Posi. tion C.6.b of Regulatory Guide 1.52, Revision 2 March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory i

Guide 1.52, Revision 2, March 1978.

e.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gause while operating the system at a flow rate of 2000 cfm f;' 10%.

i 2.

Verifying that on a recirculation signal, the system automatically switches into a recirculation mode of operation with flow through the HEPA filters and charcoal adsorber banks.

1 f.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate) of 2000 cfm

+ 10%.

s.

-s 6

MILLSTONE - UNIT 2 3/4 7-17 Amendment No. 25, 7 2 e

F

+

r w

~ - --. -...

PLANT SYSTEMS i

SURVEILLANCE REQUIREMENTS (Continued) g.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance. with ANSI N510-1975 while).perating the j

sys tem at a flow rate of 2000 cfm + 10%.

w

-s et MILLSTONE - UNIT 2 3/4 7-18 Amendment No. 7 2 O

e

m--,

6-s A s w u==w w-

.-,_.g, 1-m,

, Mm y<pe

3/4.9 REFUELING OPERATIONS' l

3/4.9.1 BORON CONCENTRATIONS LIMITING CONDITION FOR OPERATION 3.9.1 With the reactor vessel head unbolted or removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of following reactivity conditions is met:

Either a K,7f of 0.95 or less, or a.

b.

A boron concentration of greater than or equal to 1720 ppm.

APPLICABILITY: MODE 6*.

ACTION:

With the requirements of the above specification not satisfied, within 15 minutes suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 40 gpm of boric acid solution at or greater than the required refueling water storage tank' l

concentration (ppm) until K is reduced to less than or equal to 0.95 or the boron concentration is rest 8fbd to greater than or equal to 1720 ppm, whichever is the more restrictive. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:

a.

Removing or unbolting the reactor vessel head, and b.

Withdrawal of any full length CEA in excess of 3 feet from its fully inserted position within the reactor pressure vessel.

4.9.l.2 The boron concentration of all filled portions of'the reactor coolant system and the refueling canal shall be determined by chemical analysis at least l

once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

l w

i l

The reactor shall be maintained in MODE 6 whenever the reactor vessel head is unbolted or removed and fuel is in the reactor vessel.

MILLSTONE - UNIT 2 3/4 9-1 Amendment' No. 67, 7 2 l

9 4

=

REFUELING OPERATIONS -

INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 As a minimum, two source range neutron flux monitors shall be operating, each with continuous visual indication in the control room i

and one with audible indication in the containment.

APPLICABILITY: MODE 6.

ACTION:

With the requirements of the above specification not satisfied, imediately' suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

~.

SURVEILLANCE REQUIREMENTS i

4.9.2 Each source range neutron flux monitor shall be demonstrated OPERAELE by performance of:

a.

A CHANNEL FUNCTIONAL TEST at least once per 7 days.

i b.

'A CHANNEL FUNCTIONAL TEST within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the start of CORE. ALTERATIONS, and c.

A CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during CORE l

ALTERATIONS.

s

-3 t

i m

l i,

iILLSTONE - UNIT 2 3/4 9-2.

l n --nn

l

~

I TABLE 3.9-1 ACCESS DOORS TO SPENT FUEL POOL AREA Door No.

Elevation Location _

Type Area Serviced'

~

2 91 14'6" M.7 - 18.5 Double Door S'FP Skimmer System I

~

292 14 6" R/S - 18.9 Double Door Solidification System or or 8' Rollup Door 207 293 14'6" Q/R - 18.0

' Double Door Maintenance Shop 208 14'6" S - 18.9,

16' Rollup Door Railway Access 294 14'6" Q - 20.7 Single Door.

D/G Room 295 38'6" F.8 - 18 8' Rollup Door Aux. & R. W. HVAC 296 38'6" F.8 - 18.5 Single Door Aux. & R. W. HVAC

~297 38'6" F.8. - 18.5 Single Door North Stairwell 38'6"

'H.4 - 18.9 Double Sliding Door Elevator

~

298 38'6" M.4 - 18.9 Single Door Penetration Room 299 38'6" M.7 - 18.9 Double Door Main Exh. Fan Room 247 38'6" M.7 - 17.2 Single Door South Stairwell 254-,

55'6" S - 17.2 Single Door Roof Above Storage Floor 253 55'6" S - 18.9 Sir.gle Door Roof Above F. O. Tanks MILLSTONE - UNIT 2 3/4 9-15 Amendment No. 60 i

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REFUELING OPERATIONS.

STORAGE POOL AREA VENTILATION SYSTEM - FUEL STORAGE LIMITING CONDITION FOR OPERATION 3.9.15 At least one Enclosure Building Filtration System shall be OPERABLE and capable of automatically initiating operation in the.auxil-iary exhaust mode and exhausting through HEPA' filters and charcoal adsorbers on a storage pool area high radiation signal.

APPLICABILITY: WHENEVER IRRADIATED FUEL IS IN THE STORAGE P00L.

ACTION:

With the requirements.of the above specification not satisfied, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool until at least one spent fuel storage pool ventilation system is restored to OPERABLE status.

SURVEILLANCE REQUIREMENTS 4.9.15 The above required Enclosure Building Filtration 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 that the system operates for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heaters on.

b.

At least once per 18 months or (1) after any structural maintenance' on the HEPA filter or charcoal adsorber housing's, or (2) following painting, fire or chemical release in any ventilation zone communi-cating with the system by:

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MILLSTONE - UNIT 2 3/4 9-16.

. Amendment No. 7g t

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REFUELING OPERATIONS SURVEILLANCE REQUIRE!iENTS (Continued) 1.

Verifying that the cleanup system satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.S.a. C.5.c and C.S.d of Regulatory Guide 1.52, Revi-sion 2, March 1978, and the system fios rate is 9000 cfm 110%.

2.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets -the laboratory testing criteria of Regulatory Position C.S.a of Regulatory Guide,1.52, Revision 2, March 1978.

3.

Verifying a system flow rate of 9000 cfm i 10% during system.

operation when tested in accordance with ANSI N510-1975.

c.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 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, meets the laboratory testing criteria of Regulatory Position C.6.a of Regu.latory Guide 1l52, Revision 2, March 1978.

d.

At least once per 18 months by:

l.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is 16 inches Water Gauge while operating the system at a flow rate of 9000 cfm 110%.

2.

Verifying that on a Spent Fuel Storage Pool Area high radiation signal, the system automatically starts (unless already operating) and directs its exhaust flow through the HEPA filters and charcoal adsorber banks.

e.

Af ter each complete) e partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99% of the D0P when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 9000 cfm 110%.

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MILLSTONE - UNIT 2 3/4 9-17 Amendment No. 7 2

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I REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued)

Af ter each complete or par'ial replacement of a charcoal adsorber f.-

bank by verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 9000 cfm + 10%.

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3/4.10 SPECIAL TEST EXCEPTIONS SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of CEA worth and shutdown margin provided reactivity equivalent to at least the highest estimated CEA worth is available for trip insertion from OPERABLE CEA(s).

APPLICABILITY: MODES 2 and 3.

ACTION:

a.

With any full,leng'th CEA not fully inserted and with less than the a'bove reactivity equivalent available for trip. insertion, within 15 minutes initiate and continue boration at > 40 gpm of boric acid solution at or greater than the required refueling water storage tank (RWST) concentration (ppm) until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

b.

With all full length CEAs inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at > 40 gpm of boric acid solution at or greater than the required refueling water storage tank (RWST) concentration (ppm) until the SHUTOOWN MARGIN required by Specification 3.1.1.1 is restored.

SURVEILLANCE REQUIREMENTS 4.10.1.1 The position of each full length CEA required either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each.CEA not fully inserted shall be demonstrate'd capable of full insertion when tripped from at least the 50% withdrawn position within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing the SHUTDOWN MARGIN to less than the limits of Speci fication 3.1.1.1.

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MILLSTONE - UNIT 2 3/4 10-1 Amendment No. 32, 67, 7 p

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SPECIAL TEST EXCEPTIONS GROUP HEIGHT AND INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.10.2 The requirements of Specifications 3.1.1. 4, 3.1. 3.1, 3.1. 3. 2, 3.1. 3.5, l 3.1.3.6, 3.2.2, 3.2.3 and 3.2.4 may be suspended during the performance of PHYSICS TESTS provided:

a.

The THERMAL POWER is restricted to the test power plateau which shall not exceed 85% of RATED THERMAL POWER, and b.

The limits of Specification 3.2.1 are maintained and determined as specified in Specification 4.10.2 below.

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APPLICABILITY: MODES 1 and 2.

ACTION:

With any of the limits' of Specification 3.2.1, being exceeded while the requirements of Specifications 3.1.1. 4, 3.1. 3.1, 3.1. 3. 2, 3.1.3. 5, 3.1.3.6, l

3.2.2, 3.2.3 and 3.2.4 are suspended, immediately:

a.

Reduce THERMAL POWER sufficiently to satisfy the requirements of Specification 3.2.1 or b.

Be in HOT STANDBY within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be determined at least once per hour during PHYSICS TESTS in which the requirements of Specifications 3.1.1.4, l

3.1.3.1, 3.1.3.2, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3 or 3.2.4 are suspended and-shall be verified to be within the test power plateau.

4.10.2.2 The linear heat rate shall be determined to be within the limits of Specification 3.2.1 by monitoring it continuously with the IncoreDetectorMonitoringSystempursuanttotherequirementsofSpecifY- [

cations 4.2.1.3 and 3.3.3.2 during PHYSICS TESTS above 5% of RATED THEMAL POWER in which the requirements of Specifications 3.1.1.4, 3.1.3.1, 3.1. 3. 2, l

3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3 or 3.2.4 are suspended.

MILLSTONE - UNIT 2 3/4 10-2 Amendment No. 38, 52

REACTIVITY CONTROL SYSTEMS BASES 3/4.1.2 B0 RATION SYSTEMS (Continued)

The boron capability required below 200*F is based upon providing a 2% ak/k SHUTDOWN MARGIN at 140*F during refueling with all full and part length control rods withdrawn.

This condition requires either 5,050 gallons of 6.25% boric acid solution from the boric acid tanks or 57,000 gallons of 1720 ppm borated water from the refueling water storage tank.

A minimum boron concentration of 1720 ppm is required in the RWST at all times in order to satisfy safety analysis assumptions for boron dilution incidents and other transients using the RWST as a borated water source.

3 /4.1. 3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN ttARGIN is l

maintained, and (3) the potential effects of a CEA ejection accident are l

limited to acceptable levels.

The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original criteria are met.

The ACTION statements a'pplicable to an immovable or untrippable C.EA and

> 20 steps) of two or more CEAs, require a prompt to a.large misalignment (Tnce either of these conditions may be indicative shutdown of the reactor s of a possible loss of mechanical functional capability of the CEAs and in the event of a immovable or untrippable CEA, the loss of SHUTOOWN MARGIN.

For small misalignments (< 20 steps) of the CEAs, there is 1) a small degradation in the peaking facto'rs relative to those assumed in generating LCOs and LSSS setpoints for DNBR and linear heat rate, 2) a small effect on the time dependent long term power distributions relative to those used in generating LCOs and LSSS setpoints for DNBR and linear heat rate, 3) a small effect on the available SHUTDOWN MARGIN, and 4) a small effect s.

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on the ejected CEA worth used in the safety analysis. Ther'efore, the l

ACTION statement associated with the small misalignment of a CEA permits

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a onc hour time 1.nterval during which attempts may be made to restore the l

CEA to within its alignment requirements prior to initiating a reductiot in' THERMAL POWER. The one hour time limit is sufficient to- (1) identify

causes of a misaligned CEA, (2) take appropriate corrective action to

realign the CEAs and (3) minimize the effects of xenon redistribution.

i Overpower margin is provided to protect the core in the event of a large misalignment (> 20 steps) of a CEA. "However', this misalignment would cause distortion of the core power distribution. The reactor i

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WILLSTONE~- UNIT 2 B 3/4.1-3 f.mendment !!o: II,f f, 7 'i

REACTIVITIY CONTROL SYSTEMS BASES 3/4.1.3 MOVABLE CONTROL ASSEMBLIES (Continued) protective system would not detect the degradation in radial peaking factors and since variations in other system parameters (e.g., pressure i

and coolant temperature) may not be sufficient to cause trips, it is possible that the reactor could be operating with process variables less conservative than those assumed in generating LC0 and LSSS setpoints.

Therefore, the ACTION statement associated with the large. misalignment of a CEA requires a prompt and significant reduction in THERMAL POWER prior to attempting realignment of the misaligned CEA.

The ACTION statements applicable to misaligned or inoperable CEAs include requirements to align the OPERABLE CEAs in a given group with the inoperable CEA.

Conformance with these alignment requirements bring the core, within a short period of time, to a configuration consistent with that assumed in generating LCO.and LSSS setpoints. However, extended operation with CEAs significantly inserted in the core may lead td perturbations in 1) local burnup, 2) peaking factors and 3) available shutdown margin which are more adverse than the conditions assumed to exist in the safety analyses and LCO and LSSS setpoints determination.

Therefore, time limits have been imposed on operation with inoperable CEAs to preclude such adverse conditions from developing.

Operability of the CEA position indicators (Specification 3.1.3.3) is required to determine CEA positions and thereby ensure compliance with the CEA alignment and insertion limits and ensures proper operation of the rod block circuit. The CEA " Full In" and " Full Out" limits provide an additional independent means for determining the CEA positions when the CEAs are at either their fully inserted or fully withdrawn positions.

Therefore, the ACTION statements applicable to inoperable CEA position indicators permit continued operations when the positions of CEAs with inoperable position indicators can be verified by the "Ful.1 In" or " Full

'Out" limits.

CEA positions and OPERABILITY of the CEA position indicators are c

required to be verified on a nominal basis of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with more frequent verifications required if an automatic monitoring channel is s

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inoperable. These verification frequencies are adequate for assuring that the applicable LC0's are satisfied.

The maximum CEA drop time permitted by Specification 3.1.3.4 is the, assumed CEA drop time used in the accident analyses. Measurement with 515'F and with all reactor coolant pumps operating ensures that the T

1 avg measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.

MILLSTONE - UNIT 2 B 3/4 1-4 Amendment No..38

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REACTOR COOLANT SYSTEM BASES for piping, pumps and valves. Below this temperature, the system pressure must be limited to a maximum of 20% of the system's hydrostatic test f

pressure of 3125 psia.

The number of reactor vessel irradiation surveillance spec.imens and the frequencies for removing and testing these specimens are provided in Table 4.4-3 to assure compliance with the requirements of Appendix H to 10 CFR Part 50.

The limitations imposed on the pressurizer heatup and cooldown rates and spray water temperature differential are provided to assure that the pressurizer is operated within the design criteria assumed for the fati-gue analysis performed in accordance with the ASME Code requirements.

The OPERABILITY of two PORVs or an RCS vent opening of greater than 1.3 square inches ensures that the RCS will be protected.from pressure transients which could exceed the limits of Appendix G to 10 CFR Part 50 when one or more of the RCS cold legs are < 275 F.

Either PORV has adequate relieving capability to protect the RCS from overpressurization when the transient is limited to either (1) the start of an idle RCP with the secondary water temperature of the steam generator < 43 F (31*F when measured by a surface contact instrument) above tee coolant temperature in the reactor vessel or (2) the start of a HPSI pump and its injection into a water solid RCS.

3/4.4'.10 STRUCTURAL INTEGRITY The inservice inspection and testing programs for ASME Code Class 1, 2 and 3 components ensure that the structural integrity and operational readiness of these components will be maintained at an acceptable level throughout the life of the plant. These programs are in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50.55a(g) except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50.55a(g)(6)(i).

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MILLSTONE - UNIT 2 B 3/4'4-11 Amendment No. 30, 70

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-s MILLSTONE - UNIT 2 B 3/4 4-12 Amendment No. 70, 7 2 G

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J 3/ 4.' 5 EMERGENCY CORE COOLING SYSTEMS'(ECCS)

BASES 3/4.5.1 SAFETY INJECTION TANKS The OPERABILITY of each of the RCS safety injection tanks ensures that a sufficient volume of borated water will be immediately forced into the reactor core through each of the cold legs in the event the RCS pressure falls below the pressure of the safety injection tanks. This initial surge of water into the core provides the initial cooling mechanism during large RCS pipe ruptures.

The limits on safety injection tank volume, boron concentration and pressure ensure that the: assumptions used for safety injection tank injection in the accident analysis are met.

The limit of one hour for operation with an inoperable safety injection tank minimizes the time exposure of the plant to a LOCA event occurring con-current with failure of an additional safety injection tank which may result in unacceptable peak cladding temperatures.

3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS The OPERABIt'ITY of..two separate and independent ECCS subsystems ensu'res that sufficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration.

Either subsystem operating in conjunction with the safety injection tanks is capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated break sizes ranging from the double ended break of the largest RCS cold leg pipe downward.

The trisodium phosphate.dodecahydrate (TSP) stored in dissolving baskets located in the containment basement is provided to minimize the possibility of corrosion cracking of certain metal components during operation of the ECCS following a LOCA. The TSP provides this protection by dissolving in the sump' water and causing its final pH to be raised to > 7.0.

This determination assumes the RCS, the SI tanks, and the RWST is at a maximum boron concentration of 2400 ppm.

The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the accident analyses are met and that subsystem OPERABILITY is maintained. The requirement to dissolve a representative sample of TSP in a sample of RWST water provides assurance tha't the stored TSP will dissolve in borated wate,r at the postulated-

post LOCA temperatures. The ECCS leak rate surveillance requirements assure that the leakage rates assumed for the system outside containment during the recirculation phase will not be exceeded.

MILLSTONE - UNIT 2 B 3/4 5-1 Amendment No. 67, 7 9 O

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EMERGENCY CORE COOLING SYSTEMS BASES The purpose of the ECCS throttle valve surveillance requirements.is to provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary '.o:

(1) prevent total pump flow from exceeding runout conditions when the system is in i

its minimum resistance configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.

3/4.5.4 RfFUELINGWATERSTORAGETANK(RWST)

The OPERABILITY of the RWST as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA. -The limits on RWST minimum. volume and boron concentration ensure that 1) sufficient water is available within containment to permit recirculation cooling flow to the core, and 2) the reactor will remain subcritical in the cold condition following mixing of the RWST and the RCS water volumes with all control rods inserted except for the most reactive control assembly. These assump-tions are consistent with the LOCA analyses.

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Amendment No. 45 MILLSTONE - UNIT 2 B 3/4 5-2 l

3/4.6 CONTAINMENT SYSTEMS BASES l

3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radio-active materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident

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This restriction, in conjunction with the leakage rate limi-analyses.

tation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

3/4.6.1.2 dONTAINMENT L$AKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the As an accident analyses at the peak accident pressure of 54 psig, P.

a added conservatism, the measured overall integrated leakage rate is i

further limited to < 0.75 L during performance of the periodic tests a

to account for possTble degradation of the containment leakage barriers between leakage tests.

The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix "J" of 10 CFR 50.

3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and leak rate given in Specifications 3.6.1.1 and 3.6.1.2.

The limitations on the air locks allow entry and exit into and out of the containment during operation and ensure through the surveillance testing that air lock leakage will not become excessive through continuous usage.

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MILLSTONE - UNIT 2 B 3/4 6-1

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CONTAINMENT SYSTEMS BASES 3/4.6.1.4 INTERNAL PRESSURE i

l I

The limitations on containment internal pressure ensure that. the j

containment peak pressure does not exceed the design pressure of 54 psig during LOCA conditions.

The maximum peak pressure obtained from a LOCA event is 53.8 psig.

l The limit of 2.1 psig for initial positive containment pressure will limit the total pressure to less than the design pressure and is consistent with the accident analyses.

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3/4.6.1.5 AIR TEMPERATURE The limitation on, containment air temperature ensures that th.e' containment peak air temperature does not exceed the design temperature of 288*F during LOCA conditions. The containment temperature limit is consistent with the accident analyses.

3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the con-tainment vessel will be maintained comparable to the original design standards for the life of the facility.

Structural integrity is required to ensure that the vessel will withstand the maximum pressure.of 53.8..

l i

psig.in the event of a LOCA. The measurement of containment tendon lift off force, the visual and metallurgical examination of tendons, anchor-ages and liner and the Type A leakage tests are sufficient to demonstrate this capability.

The surveillance requirements for demonstrating the containment's strucutral integrity are in compliance with the recommendations of Regulatory Guide 1.35 " Inservice Surveillance of Ungrouted Tendons in Prestres' sed Concrete Containment Strucutres".

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MILLSTONE - UNIT 2 B 3/4 6-2 Am'endment No. 27, 7 ;-

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3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING. ensure that:

1) the reactor will remain subcritical during CORE ALTERATIONS, and 2) a uniform boron concentration is maintained for reactivity control in the water i

volume having direct acces<, to the reactor vessel.

These limitations are consistent with the initial conditions assumed for the boron dilution incident in the accident analyses.

3/4.9.2 INSTRUMENTATION The OP5RABILITY of the source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.

3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel ensures that sufficient time has elapsed to allow the '

radioactive decay of the short lived fission products. This decay time is consistent with the assumptions. used in the accident analyses.

3/4.9.4 CONTAINMENT PENETRATIONS The requirements on containment penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment.

The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressur-ization potential while in the PEFUELING MODE.

e 3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling "

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station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during fuel or CEA movement within the reactor pressure vessel.

MILLSTONE - UNIT 2 B 3/4 9-1,

. Amendment No. 7 g

REFUELING OPERATIONS BASES 3/4.9.6 CRANE OPERABILITY - CONTAINMENT BUILDING The OPERABILITY requirements of the cranes used for movement of fuel assemblies ensures that: 1) each crane has sufficient load capacity to lift a fuel element, and 2) the core internals and pressure vessel are protected from excessive lif ting force in the event they are inadvertently engaged during lif ting operations.

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel assembly and CEA over irradiated fuel assemblies ensures that no more than the contents of one fuel assembly will be ruptured in the event of a fuel hand-ling accident. -This assumption is consistent with the activity release assumed in the accident analyses.

3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140 F as required during the REFUELING MODE, and (2) sufficient coolant circulation ~ 1s maintain ~ed through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.

The requirement to have two shutdown cooling loops OPERABLE when the ' refuel pool is unavailable as a heat sink ensures that a single failure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capability. With the reactor vessel water level at or above the vessel flange, the reactor vessel pit seal installed, and a combined available volume of water in the refueling pool and refueling water storage tank in excess of 370,000 gallons, a large heat sink is. readily available for core cooling. Adequate time is thus available to initiate emergency procedures to provide core cooling in the event of a failure of the operating shutdown cooling loop.

3/4.9.9 and 3/4.9.10 CONTAINMENT RADIATION MONITORING AND CONTAINMENT PURGE VALVE ISOLATION SYSTEM The OPERABILITY of these systems ensures that the containment purge valves will be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITY of these systems is required to restrict the release of radioactive material from the containment atmosphere to the enxirocaent.

3/4.9.11 and 3/4.9.12 WATER LEVEL-REACTOR VESSEL AND STORAGE POOL WATER LEVEL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly..The minimum water depth is consistent with the assumptions of the accident analysis.

MILLSTONE - UNIT 2 B 3/4 9-2 Amendment No. 63, 71 as

_.________._________________j

v t e Letter Sequence Other
TAC:47471, (Approved, Closed) TAC:47472, (Approved, Closed)
Initiation Request Acceptance... Administration Questions Answers Results Approval Other: B10325, Forwards Reload Safety Analysis Submitted in Support of Cycle 5 Reload.Rept Includes Results of Boron Dilution,Loss of Reactor Coolant Flow,Seized Rotor Reanalysis & Control Element Assembly Ejection & Withdrawal at Critical, ML20033A519, ML20039C038, ML20041D017, ML20041D021
MONTHYEAR1981-12-17 [Table View]

ML20041D017

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