ML20133N937

Amend 101 to License DPR-65,changing Tech Specs to Delete Ref to Station Emergency Procedure & Revise Surveillance Requirement to Make Diesel Generator Testing Consistent W/Requirements of Generic Ltr 83-30

ML20133N937
Person / Time
Site:	Millstone
Issue date:	08/02/1985
From:	Butcher E Office of Nuclear Reactor Regulation
To:
Shared Package
ML20133N940	List: ML20133N937 ML20133N948
References
GL-83-30, TAC-57423, TAC-57424, TAC-57425, TAC-57426, TAC-57427, NUDOCS 8508140065
Download: ML20133N937 (17)

Text

. _ _ _ _ _ _ _ _ _ _

UNITED STATES g

NUCLEAR REGULATORY COMMISSION t

l wassiscios, o. c. rosss

\\...../

NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 101 License No. DPR-65 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The applications for amendment by Northeast Nuclear Energy Company, etal.(thelicensee),datedMarch28, March 29(3),and April 4,1985, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Comission;

' C.

Thereisreasonableassurance(1)thattheactivitiesauthorizedby 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 comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

0500140065 050002 DR ADOCK 050 6

. 2.

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. DPR-65 is hereby amended to read as follows:

(2) Technical Specifications The Tecunical Specifications contained in Appendices A and B, as revised through Amendment No.101, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 0

Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications D'aleofIssuance: August 2, 1985 I

ATTACHMENT TO LICENSE AMENDMENT N0.101 FACILITY OPERATING LICENSE N0. DPR-65 DOCKET N0. 50-336 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 provided to maintain document completeness.

Remove Pages Insert Pages 3/4 3-27 3/4 3-27 3/4 4-7 3/4 4-7 3/4 4-9 3/4 4-9 3/4 5-5 3/4 5-5 3/4 7-8 3/4 7-8 3/4 7-13 3/4 7-13 3/4 8-4 3/4 8-4

1 3

. TABLE 3.3-6 h

RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION c-5*

1.

AREA MONITORS m

a.

Spent Fuel Storage 1 100 mR/hr 10-I - 10*4 mR/hr 13 and 15 Criticality Monitor 2

and Ventilation System Isolation 4

b.

Control Room Isolation 1

ALL MODES 1 2 mR/hr 10'I - 10 mR/hr 16 2.

PROCESS MONITORS w

b a.

Containment 1

ALL MODES **

1 the value 10 - 10+6 cpm 14 and (a) l Atmosphere-Particulate determined in accordance with Specification 4.3.2.1.4.

b.

Containment 1

ALL MODES **

< the value 10 - 10+6 cpm 14 and (a) l p

Atmosphere-Gaseous ifetermined in E.

accordance with 2

Specification 5

4.3.2.1.4.

!?

• With fuel in storage building.

g **These radiation monitors are not required to be operable during Type "A" Integrated Leak Rate Testing.

l e

f e

TABLE 3.3-6 (Continued)

TABLE NOTATION (a)

During MODE 6, also comply with the ACTION requirements of Specification 3.9.9, as applicable.

ACTION 13 -

With the number of area monitors OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 14 -

With the number of process monitors OPERABLE less than required b either (a)y the Minimum Channels OPERABLE requirement obtain and analyze grab samples of the moni-tored parameter at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or (b) use a Constant Air Monitor to monitor the parameter.

ACTION 15 -

With the number of area monitors OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.0.13.

ACTION 16 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.

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MILLSTONE - UNIT 2 3/4 3-28 Amendment No. 7E,100

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.1.3 Inspection Frequencies - The above required inservice inspections of steam generator tubes shall be performed at the following frequencies:

a.

The first inservice inspection shall be performed after 6 Effective Full Power Months but within 24 calendar months of initial criticality. Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection.

If two consecutive inspections following service under AVT conditions, not including the preservice inspection, result in all inspec-tion results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the-inspection interval may be extended to a maximum of once per 40 months.

b.

If the results of the inservice inspection of a steam generator C' conducted in accordance with Table 4.4-6 at 40 month intervals fall into Category C-3, the inspection frequency shall be increased to at least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspec-tions satisfy the criteria of Specification 4.4.5.1.3.a; the interval may then be extended to a maximum of once per 40 months.

Additional, unscheduled inservice inspections shall be performed c.

on each steam generator in accordance with the first sample inspection specified in Table 4.4-6 during the shutdown subsequent

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to any of the following conditions:

1.

Priamry-to-secondary tubes leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2.

I 2.

A seismic occurrence greater than the Operating Basis Earthquake.

3.

A loss-of-coolant accident requiring actuation of the engineered safeguards.

4.

A main steam line or feedwater line break.

MILLSTONE - UNIT 2 3/4 4-7 Amendment No. 22, 37, 83, 101 w

m r--

REACTOR COOLANT SYSTEM 1

SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.1.4 Acceptance Criteria a.

As used in this Specification 1.

Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.

2.

Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.

3.

Degraded Tube means a tube containing imperfections >20%; of the nominal wall thickness caused be degradation.

4.

% Degradation means the percentage of the tube wall thickness affected or removed by degradation.

5.

Defect means an imperfection of such severity that it exceeds the plugging limit. A tube or sleeve containing a defect is defective.

g 6.

Plugging Limit means the imperfection depth at or beyond which the tube or sleeve shall be repaired because it may become

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unserviceable prior to the next inspection and is equal to 40%

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of the nominal tube wall thickness for tubes.*

7.

Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line

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break as specified in 4.4.5.1.3.c above.

i 8.

Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U - Bend to the top support of the cold leg.

b.

The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or sleeve all tubes exceeding the l

plugging limit and plug all defective sleeves) required by Table 4.4-6.

MILLSTONE - UNIT 2 3/4 4-7a Amendment No. 22, 37, 52, 89

• The plugging limit for sleeves will be determined prior to next refueling outage.

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REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE, b.

1 GPM UNIDENTIFIED LEAKAGE, c.

1 GPM total primary-to-secondary leakage through both steam generators and 0.5 GPM through any one steam generator, and I

d.

10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a.

With any PRESSURE BOUNDARY LEAKAGE, be in COLD SHUTDOWN within

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36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

b.

With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in COLD SHUT-DOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

• m.

SURVEILLANCE REQUIREMENTS 4.4.6.2 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:

a.

Monitoring the containment atmosphere particulate radioactivity 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 sump inventory 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.

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 /> during steady state operation except when operating in the shutdown cooling mode.

MILLSTONE - UNIT 2 3/4 4-9 Amendment No. 25, 37, 77, 83,101 N

a

REACTOR COOLANT SYSTEM CHEMISTRY LIMITING CONDITION FOR OPERATION 3.4.7 The Reactor Coolant System chemistry shall be maintained within the limits specified in Table 3.4-1.

APPLICABILITY: ALL MODES.

ACTION:

MODES 1, 2, 3 and 4 a.

With any one or more chemistry parameter in excess of its Steady State Limit but within its Transient Limit, restore the parameter to within its Steady State Limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

b.

With any one or more chemistry parameter in excess of its Transient Limit, be in COLD SHUTDOWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

MODES 5 and 6 With the concentration of either chloride or fluoride in the Reactor Coolant System in excess of its Steady State Limit for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or in excess of its Transient Limit, reduce the pressurizer pressure to < 500 psia, if applicable, and perform an analysis to

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determine the effects of the out-of-limit condition on the structural integrity of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operations prior to

, increasing the pressurizer pressure above 500 psia or prior to proceeding to MODE 4.

SURVEILLANCE REQUIREMENTS 4.4.7 The Reactor Coolant System chemistry shall be determined to be within the limits by analysis of those parameters at the frequencies specified in Table 4.4-1.

MILLSTONE - UNIT 2 3/4 4-10

}

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 10.

Verifying that the following valves are in the indicated position with power to the valve operator removed:

Valve Number Valve Function Valve Position 2-SI-306 Shutdown Cooling Open Flow Control 2-SI-659 SRAS Recirc.

Open*

2-SI-660 SRAS Recire.

Open*

2-CH-434 Thermal Bypass Closed **

b.

By a visual inspection which verifies that 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 inspect' ion shall be perfonned:

^

1.

For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.

Of the areas affected within containment at the completion of containment entry when CONTAINMENT INTEGRITY is established.

c.

At least once per 18 months by:

1.

Verifying automatic isolation of the shutdown cooling system from the Reactor Coolant System when the Reactor Coolant System pressure is above 300 psia.

2.

A visual inspection of the 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 corrosion.

3.

Verifying that a minimum total of 110 cubic feet of trisodium l

phosphate dodecahydrate (TSP) is contained within the TSP I

storage baskets.

4.

Verifying that when a representative sample of 0.35 + 0.05 lbs of TSP from a TSP storage basket is gubmerged, wTthout agitation, in 50 + 5 gallons of 180 + 10 F borated water from the RWST, the pH of the mixed solution is raised to

> 6 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

• To be closed prior to recirculation following LOCA.

• • 2-CH-434, a manual valve, shall be locked closed.

MILLSTONE - UNIT 2 3/4 5-5 Amendment No. 7,45,52,101

EMERGENCY CORE COOLING SYSTEMS SURVEILLI.NCE REQUIREMENTS (Continued) 5.

Verifying a total leak rate less than or equal to 12 gallons per hour for the high pressure safety injection system in conjunction with the containment spray system (reference Specification 4.6.2.1.c) at:

a)

A high pressure safety injection pump discharge pressure of greater than or equal to 1125 psig on recirculation flow, for the parts of the system between the pump discharge and the header injection valves, including the pump seals.

b)

Greater than or equal to 22 psig at the pump suction for the piping from the containment sump check valvd to the pump suction.

MILLSTONE - UNIT 2 3/4 5-Sa Amendment No. 61

1

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PLANT SYSTEMS ACTIVITY LIMITING CONDITION FOR OPERATION 3.7.1.4 The specific activity of the secondary coolant system shall be

< 0.10 pCi/ gram DOSE EQUIVALENT I-131.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the specific activity of the secondary coolant system > 0.10 uCi/

gram DOSE EQUIVALENT I-131, be in COLD SHUTDOWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> after detection.

SURVEILLANCE REQUIREMENTS 4.7.1.4 The specific activity of the secondary coolant system shall be determined to be within the limit by performance of the sampling and analysis program of Table 4.7-2.

9 MILLSTONE - UNIT 2 3/4 7-7 m

TABLE 4.7-2 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM TYPE OF MEASUREMENT MINIMUM AND ANALYSIS FREQUENCY 1.

Gross Activity Determination 3 times per 7 days with a maximum time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> between samples.

I 2.

Isotopic Analysis for DOSE a) 1 per 31 days, when-EQUIVALENT I-131 Concentration ever the gross aptivity determination indicates iodine concentrations greater than 10% of the allowable limft -

t b) 1 per 6 months, when-ever the gross activity determination indicates iodine concentrations below 10% of the allowable limit.

MILLSTONE - UNIT 2 3/4 7 8 AmendmentNo.4/d'101

PLANT SYSTEMS 3L4.7.5FLOODLEVEL LIMITING CONDITION FOR OPERATION 3.7.5.1 At least one OPERABLE service water pump motor shall be pro-tected against flooding to a minimum elevation of 28 feet Mean Sea Level USGS datum if either:

a.

The water level, including wave crest height, is exceeding plant grade level (14.0 feet Mean Sea Level USGS datum), or b.

Three or more of the following conditions are occurring simultaneously:

~~.

1.

The center of a storm, as determined by radar, recon-naissance or forecasted track projection, is presently located within the critical area as defined on Figure 3.7-1.

2.

The projected track of a storm approaching the facility as determined by radar, reconnaissance or forecasted track projection, lies between 130* and 350*.

3.

The central pressure of the storm is or is forecasted to be 1 28.0 in. Hg; or the measured 15 minute average wind speed at nominal elevation 389 on the meteorological tower exceeds 60 mph.

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4.

The 15 minute average wind direction at nominal elevation 389 on the meteorological tower is within the sector from 150" clockwise to 300*.

p APPLICABILITY: ALL MODES ACTION:

With the water level exceeding either plant grade or with three or more of the above specified meteorological conditicas being exceeded simul-taneously, immediate initiate action to protect at least one service water pump motor against flooding to a minimum elevation of 28 feet; complete this protective action within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

MILLSTONE - UNIT 2 3/4 7-13 Amendment No.101 i

M

1

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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.5.1.1 The water level shall be determined to be below plant grade at least once per hour when the eye of a hurricane is within 150 miles of the facility.

4.7.5.1.2 The above specified meteorological conditions shall be deter-mined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> when a hurricane eye is within 150 miles of the facility. The meteorological conditions shall be determined from forecasts obtained from the Connecticut Valley, Electrical Exchange (CONVEX) and from the site meterological instrumentation.

a

.e

• 96*

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D

• MILLSTONE - UNIT 2 3/4 7-14

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

At least once per 92 days by verifying that a sample of diesel fuel from each of the three fuel oil storage tanks, obtained in accordance with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM D975-74 when checked for viscosity, water and sediment.

c.

At least once per 18 months during shutdown by:

1.

Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service.

2.

Verifying that the automatic time delay sequencer is OPERABLE with the following settings:

er*.

Sequence Time After Closing of Diesel Generator Step Output Breaker (Seconds)

Minimum Maximum 1 (T )

1.5 2.2 j

8.4 2 (T )

Tj + 5.5 2

14.6 3 (T )

T2 + 5.5 3

4 (T )

T3 + 5.5 20.8 4

3.

Verifying the generator capability to reject a load of

~

> 250 kw and maintain voltage at 4160 1 500 volts and Trequency at 6013 Hz.

4.

Verifying the generator capability to reject a load of 1300 Kw without exceeding the overspeed trip setpoint.

5.

Simulating a loss of offsite power in conjunction with a safety injection actuation signal, and:

a)

Verifying deenergization of the emergency busses and load shedding from the emergency busses, b)

Verifying the diesel starts from ambient condition on the autostart signal, energizes the emergency busses with pennanently connected loads, energizes the auto-connected emergency loads through the load sequencer and operates for > 5 minutes while its generator is loaded with the emergency loads.

MILLSTONE - UNIT 2 3/4 8-3 Amendment No. 45

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c)

Verifying that on the safety injection actuation signal, all diesel generator trips, except engine overspeed, generator differential current, voltage restraint overcurrent, and low lube oil pressure (2 out of 3) are automatically bypassed.

6.

Verifying the diesel generator operates for > 60 minutes '

while loaded to > 2750 kw.

7.

Verifying that the auto-connected loads to each diesel generator do not exceed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating of 3000 kw.

MILLSTONE - UNIT 2 3/48-4 Amendment No. /M/ > 101

-