ML20154N227

Amend 18 to License NPF-49,revising Tech Spec Section 3.4.9.3 to Change Min RCS Vent Area Required for Cold Overpressure Protection from 7.0 to 5.4 Inches & Tech Spec Sections 3.8.1.2,3.8.2.2 & 3.8.3.1 for Consistency

ML20154N227
Person / Time
Site:	Millstone
Issue date:	05/19/1988
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20154N197	List: ML20154N193 ML20154N227 ML20154N240
References
NUDOCS 8806020236
Download: ML20154N227 (13)

Text

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UNITED STATES

b  %,*t, NUCLEAR REGULATORY COMMISSION 3 .j wAssiNoToN. o. c. 20553

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NORTHEAST NLCLEAR ENERGY COMPANY J &

• DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION n UNIT NO. 3 ANENOMENT TO FACILITY OPERATING LICENSE Amendment No.18 License No. NPF-49

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

A. The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated February 18, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (1) 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 Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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• Northeast Nuclear Energy Company is authorized to act as agent and represent-ative for the following Owners: Central Maine Power Company, Central Vermont Public Service Corporation, Chicopee Municipal Lighting Plant, City of Burlington, Vermont, Connecticut Municipal Electric Light Company, Massachusetts Municipal Wholesale Electric Company, Montaup Electric Company, New England Power Company, The Village of Lyndonville Electric Department, Western

Massachusetts Electric Company, and Vermont Electric Generation and Transmission Cooperative, Inc., and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

l 8806020236 800519 3 DR ADOCK 0500

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2. Accordingly, the license is amended by changes to the Technical Specific 3tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No NPF-49 is hereby amended to read as follows:

(2) I!Ehgiga!,Segg!f!gatiggs The Technical Specifications contained in Appendix A, as revised i

through Amendment No.18 , and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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

FOR THE t'UCLEAR REGULAT RY COMMISSION Je Uf r F. Stolz, Director h '

LMoject Directorate 1-4 Division of Reactor Projects 1/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 19,1988

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ATTACHMENT TO LICENSE _A[t,ENDfEtH_h,0 18 FACILT!Y OPERATING LICENSE NO. NPF-49 DOCKE1 NO. 5,0342,3 .

Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by atendment nur.ber and centain vertical lines indicating the areas of change. The corresponding overleaf pages are provided to raintain docurent completeness.

Remove Insert 3/4 4-38 3/4 4-38 3/4 8-9 3/4 8-9 3/4 8-14 < 3/4 8-14 3/4 8-17 3/4 8-17 B3/4 4-15 B3/4 4-15 i

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REACTOR COOLANT SYSTEM PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.9.2 The pressurizer temperature shall be limited to:

a.

A maximum heatup of 100'F in any 1-hour period, b.

A maximum cooldown of 200*F in any 1-hour period, and

c. A maximum spray water temperature differential of 320 F.

APPLICABILITY: At all times.

ACTION:

With the pressurizer temperature limits in excess of any of the above limits, restore the temperature to within the limits within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the pressurizer; determine that the pressurizer remains acceptable for continued operation or be in at least HOT STAN0BY within the next 6 hou.'s and reduce the pressurizer pressure to less than 500 psia within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.9.2 The pressurizer temperatures shall be determined to be within the limits at least once per 30 minutes during system heatup or cooldown. The spray water temperature differential shall be determined to be within the limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during auxiliary spray operation.

. 3 HILLSTONE - UNIT 3 3/4 4-37 l _

J REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LlHITING CONDITION FOR OPERATION 3.4.9.3 At least one of the following Overpressure Protection Systems shall be OPERABLE:

a. Two residual heat removal (RHR) suction relief valves each with a setpoint of 450 psig, or

b. Two power-operated relief valves (PORVs) with lift settings which do not exceed the limit established in Figure 3.4-4a or Figure 3.4-4b,', as a~propriate, p or

c. The Reactor Coolant System (RCS) depressurized with an RCS vent of greater than or equal to 5.4 square inches.

APPllCABilITY: MODE 3 when the temperature of any RCS cold leg is less than or equal to 350'F, MODES 4 and 5, and MODE 6 with the reactor vessel head on.

ACTION:

a. With one required PORV inoperable or one required RHR suction relief valve inoperable, restore two PORVs or two RHR suction relief valves to OPERABLE status within 7 days or depressurize and vent the RCS through at least a 5.4 square inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />,

b. With both required PORVs inoperable, within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> either restore both RHR suction relief valves to OPERABLE status or depressurize and vent the RCS through at least a 5.4 square inch vent.

c. With both required RHR suction relief valves inoperable, within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> either restore both PORVs to OPERABLE status or depressurize and vent the RCS through at least a 5.4 square inch vent.

d. In the event the PORVs, the RHR suction relief valves, or the RCS vent (s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Cossnission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs, the RHR suction relief valves, or RCS vent (s) on the transient, and any corrective action necessary to prevent recurrence,

e. The provisions of Specification 3.0.4 are not applicable.

MILLSTONE - UNIT 3 3/4 4-38 Amendment No.18

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l 11[CTRIC AL POWER SYSTEMS A.C. SOURCES SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a. One circuit between the offsite transmission network and the Onsite Class IE Distribution System, and

b. One diesel generator with:

1) A day tank containing a minimum volume of 205 gallons of fuel,

2) A fuel storage system containing a minimum volume of 32,760 gallons of fuel,

3) A fuel transfer pump,

4) Lubricating oil storage containing a minimum total volume of 280 gallons of lubricating oil, ant'

5) Capability to transfer lubricating oil from storage to the diesel generator unit.

APPLICABillTY: MODES 5 and 6.

ACTION:

With less than the above minimum required A.C. electrical power sources OPERABLE, inrediately suspend all operations involving CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel, or crane operation with loads over the fuel storage pool, and within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, depressurize and vent the Reactor Coolant System through a greater than or equal to 5.4 square inch vent. In addition, when in MODE 5 with the reactor coolant loops not filled, or in MODE 6 with the water level less than 23 feet above the reactor vessel flange, imediately initiate corrective action to restore the required sources to OPERABLE status as soon as possible.

SURVEILLANCE RE0VIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be l demonstrated OPERABLE by the performance of each of the requirements of Specifications 4.8.1.1.1, 4.8.1.1.2 (except for Specification 4.3.1.1.2a.6, and 4.8.1.1.3.

l l MILLSTONE - UNIT 3 3/4 8 9 Amendment No. 18 l

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I ELECTRICAL POWER SYSTEMS 3/4.8.2 D.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.2.1 As a minimum, the following 0.C. electrical sources shall be OPERABLE:

a. 125-volt Battery Bank 301A-1, and an associated full capacity charger,

b. 125-volt Battery Bank 301A-2, and an associated full capacity charger,

c. 125-volt Battery Bank 3018-1 and an associated full capacity charger, and

d. 125-volt Battery Bank 3018-2 and an associated full capacity charger.

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

ACTION:

a. With either Battery Bank 301A-1 or 3018-1, and/or one of the required full capacity chargers inoperable, restore the inoperable battery bank and/or full capacity charger to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />,

b. With either Battery Bank 301A-2 or 301B-2 iroperable, restore the inoperable battery bank to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.9.2.1 Each 125-volt battery bank and charger shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying that:

1) The parameters in Table 4.8-2a meet the Category A limits, and

2) The total battery terminal voltage is greater than or equal to 129 volts on float charge.

HILLSTONE - UNIT 3 3/4 8-10 M

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TABLE 4.8-2b BATTERY CHARGER CAPACITY CHARGER AMPERAGE 301A-1 200 301A-2 50 301A-3 200 301B-1 200 301B-2 50 301B-3 200 MILLSTONE - UNIT 3 3/4 8-13

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ELECTRICAL POWER SYSTEMS D.C. SOURCES SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.2 As a minimum, one 125-volt battery bank and full-capacity charger shall be. OPERABLE. its associated APPLICABILITY: MODES 5 and 6.

ACTION:

With the required immediately suspendbattery all bank and/or full-capacity charger inoperable, operations involving CORE ALTERATIONS, positive reactivity changes, or movement of irradiated fuel; initiate corrective action to restore the required battery bank and full capacity charger to OPERABLE status as soon as possible, and within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, depressurize and vent the Reactor Coolant System through a 5.4 square inch vent.

IVRVEILLANCE RE0VIREMENTS 4.8.2.2 The above required 125 volt battery bank and full-capacity charger shall be demonstrated OPERABLE in accordance with Specification 4.8.2.1.

MILLSTONE - UNIT 3 3/4 8-14 Amendment No. 18

ELECTRICAL POWER SYSTEMS ONSITE POWER DISTRIBUTION SHUTDOWN LlHITING CONDITION FOR OPERATION 3.8.3.2 As a minimum, the following electrical busses shall be energized in the specified manner:

a. One train of A.C. emergency busses consisting of one 4160 volt and four 480-volt A.C. emergency busses,

b. Two 120 volt A.C. vital busses energized from their associated inverters connected to their respective D.C. busses, and

c. Two 125 volt D.C. busses energized from their af sociated battery banks.

APPLICABILITY: MODES 5 and 6.

ACTION:

With any of the above required electrical busses not energized in the required manner, immediately suspend all operations involving CORE ALTERATIONS, positive reactivity changes, or movement of irradiated fuel, initiate corrective action to energize the required electrical busses in the specified manner as soon as possible, and $ithin 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, depressurize and vent the RCS through at least a 5.4 square inch vent.

SVRVEILLANCE RE0VIREMENT3 4.8.3.2 The specified busses shall be determined energized in the required manner at least once per 7 aays by verifying correct breaker alignment and indicated voltage on the busses.

MILLSTONE - UNIT 3 3/4 8-17 knendment No.18 t

ELECTRICAL POWER'_ SYSTEMS 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVE4 CURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION --

3.8.4.1 All containment penetration conductor overcurrent protective devices given in Table 3.8-1 shall be OPERABLE.

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

ACTION:

With one or more of the containment penetration conductor overcurrent protective device (s) given in Table 3.8-1 inoperable:

a.

Restore the protective device (s) to OPERABLE status or daenergize the circuit (s) by tripping the associated backup circuit breaker or racking out or removing the inoperable circuit breaker within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, declare the affected system or component inoperable, and verify the backup circuit breaker to be tripped or the inoper-able circuit breaker racked out or removed at least once per 7 days thereafter; the provisions of Specification 3.0.4 are not applicable to overcurrent devices in circuits which have their backup circuit breakers tripped, their inoperable circuit breakers racked out, or removed, or b.

Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD l SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS I .

4.8.4.1 All containment penetration conductor overcurrent protective devices given in Table 3.8-1 shall be demonstrated OPERABLE:

a. At least once per 18 months:

l 1) By verifying that the medium voltage (4-15 kV) circuit breakers are OPERABLE by selecting, on a rotating basis, at least 10% of the circuit breakers of each voltage level, and performing the following:

a) A CHANNEL CALIBRATION of the associated protective relays, b) An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and control circuits function as designed, and MILLSTONE - UNIT 3 3/4 8-18 l

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l REACTOR COOLANT SYSTEM BASES PRESSURE /TEMPERATURElIMITS(Continued)

Follouing the generation of pressure-temperature curves for both the steady produced state and finite heatup rate situations, the final limit curves are as follows. A composite curve is constructed based on a point by point comparison of the steady-state and finite heatua rate data. At any given temperature, the allowable pressure is taken to be tie lesser of the three values taken from the curves under consideration. 1 The use of the composite curve is necessary to set conservative heatup limitations because it is possible for conditions to exist such that over the t course of the heatup ramp the controlling condition switches from the *.nside to the outside and the pressure limit must at all times be based on analysis of the most critical criterion.

Finally, the composite curves for the heatup rate data and the cooldown rate data are adjusted for possible errors in the pressure and temperature sensing instruments by the values indicated on the respective curves.

Although the pressurizer operates in temperature ranges above those for which there is reason for concern of nonductile failure., operating limits are provided to assure compatibility of operation with the fatigue analysis performed in accordance with the ASME Code requirements.

LOLD OVERPRESSURE PROTECTION The OPERABILITY of two PORVs or an RCS vent opening of at least 5.4 square inches ensures that the RCS will be protected from pressure transients which couldexceedthelimitsofAppendixGto10CFgPart50whenoneormoreof the RCS cold legs are less than or equal to 350 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 secondary water temperature of the steam generator inss than or equal to 50thg above the RCS cold temperatures, or (2) the start of a charging pump and its injection into a water-solid RCS.

The Maximum Allowed PORY Setpoint for the Cold Overpressure Protection System (COPS) is derived by analysis which models the performance of the COPS assuming various mass input and heat input transients. Operation with a PORV Setpoint less than or equal to the maximum Setpoint ensures that Appendix G criteria will not be violated with consideration for a maximum pressure overshoot beyond the PORV Setpoint which can occur as a result of time delays j in signal processing and valve opening, instrument uncertainties, and single failure. To ensure that mass and heat input transients more severe than those assumed cannot occur, Technical Specifications require lockout of all but one safety injection pump and all but one centrifugal charging pump while in MODES 4, 5, and 6 with the reactor vessel head igstalled and disallow start of an RCP if secondary temperature is more than 50 above primary temperature.

The Maximum Allowed PORV Setpoint for the COPS will be updated based on the results of examinations of reactor vessel material irradiation surveillance specimens performed as required by 10 CFR Part 50, Appendix H, and in accordance with the schedule in Table 4.4 5.

MILLSTONE - UNIT 3 8 3/4 4 15 Amendment No. 18

REACTOR COOLANT SYSTEM s

BASES 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 50.55a(g) except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(1).

Components of the Reactor Coolant System were designed to provide access to permit inservice inspections in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, 80 Edition and Addenda through Winter except where specific written relief has been granted pursuant to 10 CFR 50.55a(g)(6)(i).

3/4.4.11 REACTOR COOLANT SYSTEM VENTS Reactor Coolant System vents are provided to exhaust noncondensible gases and/or steam from the Reactor Coolant System that could inhibit natural circula-tion core cooling. The OPERABILITY of least one Reactor Coolant System vent path from the reactor vessel head and the pressurizer steam space ensures that the capability exists to perform this function.

The valve redundancy of the Reactor Coolant System vent paths serves to minimize the probability of inadvertent or irreversible actuation while ensuring that a single failure of a vent valve, power supply, or control system does not prevent isolation of the vent path.

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. The function, capabilities, and testing requirements of the Reactor Coolant l System vents are consistent with the requirements of Item II.B.1 of NUREG-0737, l "Clarification of TMI Action Plant Requirements," November.1980.

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MILLSTONE - UNIT 3 8 3/4 4-16

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