ML19332C707

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Amend 114 to License DPR-36,modifying Tech Specs to Provide up-to-date Pressure/Temp Limits for Operation of RCS During Heatup,Cooldown,Criticality & Hydrotest
ML19332C707
Person / Time
Site: Maine Yankee
Issue date: 11/14/1989
From: Wessman R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19332C706 List:
References
NUDOCS 8911280446
Download: ML19332C707 (19)
v • d • e


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UNITED STATES 3

i NUCLEAR REGULATORY COMMISSION

_j WASHINGTON, D C. 205$5 s.

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. MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309 i

MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE NN"ko 0$36 1.

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

A.

The application for amendment filed by the Maine Yankee Atomic l

Power Company (the licensee) dated December 2, 1988 complies 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 application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance: (i)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and i

safety of the public, and (11) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; l

D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and rafety of the public; and E.

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

2.

A::cordingly, the license is amended by changes to the Technical Specifica-L tions as indicated in the attachment to this license amendment, and L

paragraph 2.B.6.(b) of Facility Operating License No. DPR-36 is hereby amended to read as follows:

L (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No 114, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the l

Technical Specifications.

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This ifcense amendment is effective es of its date of issuance.

1 FOR THE NUCLEAR REGULATORY COMMISSION D

w Richard H. Wessman, Director Project Directorate I-3 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation.

Attachment:

!ph!kfk0akk!ns' Date of Issuance: November 17, 1989 i

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j ATTACHMENT TO LICENSE AMENDMENT NO.114 1

FACILITY OPERATING LICENSE NO. DPR-36 l

DOCKET NO. 50-309 1

Replace the following pages of the Appendix A Technical Specifications with the attached pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert 3

3 3.4-1 3.4-1 3.4-2 3.4-2 3.4-3 3.4-3 3.4-3a 3.4-4 3.4-4 3.4-5 3.4-5 3.4-6 3.4-6 3.4-7 3.4-7 3.4-8 3.4-8 3.4 3.4-9 3.4-10 3.4-10 3.4-11 3.4-11 3.4-12*

3.4-13*

3.4-14*

3.4-15*

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Adiusted Reference Temnerature (ART)

'The initial ~ reference temperature, RTNDT, of the reactor pressure vessel adjusted for the effects of irradiation and including margin for

. uncertainties.

Lowest Service Temoerature r

Reactor coolant temperature.below which the system-pressure must be limited to a maximum of 621 psig.

Minimum Boltuo Temoerature Reactor coolant temperature below which the reactor pressure vessel head stud loads must be reduced to zero (0).

REACTOR PROTECTIVE SYSTEM Instrument Channels One of four independent measurement channels, complete with the sensors, sensor power supply units, amplifiers, and trip modules provided for each safety parameter.

Reactor Trio The de-energizing of the magnetic jack holding coils which releases the shutdown and regulating control elements (CEA's) and allows them to drop into the core.

Trio Module A bistable unit in each of the instrument channels which is tripped when the parameter. signal exceeds a specified limit. The relay contact outputs'of the trip modules' form the reactor protective system logic.

ENGINEERED SAFEGUARDS SYSTEMS Subsystem-l One of two or more redundant grouping of sensors, logic, and circuitry able to bring about automatic or manual initiation of an engineered safeguard.

Dearee of Redundancy The difference between the number of operable channels and the number of channels which when tripped will cause an automatic system trip.

- Amendment No. EB, EE, EE, 114 -

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w 3.4 COMBINED HEATUP. COOLDOWN AND PRESSURE-TEMPERATURE LIMIT 4TIONS

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Aeolicability:-

-Applies to temperature and pressure conditions during heatup and il cooldown of the reactor coolant system.

Obiective:

To maintain operational limits within design boundaries of th'e reactor coolant system.

Soecification:

A.

Reactor Coolant System q

m 1.

The reactor coolant system shall be operated within the limits set forth in Table 3.4-1 and the pressure-temperature limits derived-from (2) below.

Remedial Action:

If the reactor coolant system is subject to conditions outside of the above limits the reactor shall be brought _subtritical and an engineering analysis of the con-sequences shall be made prior to restoration of power operation.

2. 'The pressure-temperature limits for reactor coolant system operation shall be revised s.t each refueling using the fellowing procedure.
a. The pressure-temperature limits for reactor coolant system operation shall be as developed by superimposing fluence dependent heatup and cooldown limits into the basic ASME Section 3 limits of operation (Figure 3.4-1).

At each refueling the heatup and cooldown limits will be modified to account for material. property changes in the reactor vessel-projected through the next core cycle in accordance with the following procedure:

1.

Project the cumulative thermal generation, HWH(t), on the vessel through the next core cycle, 2.

Determine the associated = fluence to the vessel from Figure 3.4-2,

3. ' Determine the Adjusted Reference Temperature (ART) at the 1/4T and 3/4T from Figure 3.4-3.

4.

The heatup and cooldown limit lines at locations of l

interest in Figures 3.4-4 through 3.4-9 shall be shifted parallel to the temperature axis (horizontal) in the direction of increasing temperature, a distance equivalent to the Adjusted Reference Terrperature (ART) at the 1/4T and 3/4T as applicable.

3.4-1

~ Amendnent flo. U, S,114 i

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.The following table provides the Adjusted Reference z Temperature (ART). shift parameter to be. applied:-

APPLICABLE CURVES FIGURES SHIFT PARAMETER Heatup-Limits for 3/4T. Location 3.~4-4 & 3.4-7 3/4T ART-Heatup Limits for:

1/4T Location 3.4-5 & 3.4-8 1/4T ART-Cocidown Limits for -

1/4T Location 3.4-6 & 3.4-9 1/4T ART 5.

Superimpose the shif ted Figures 3.4-4 through 3.4-9 onto Figure 3.4-1 to provide the appropriate operational limits for heatup and cooldown during (J

normal and hydrostatic test operations.

B.

Reactor Core 1.

The reactor 'shall not be critical if the reactor coolant pressure is less than 400 psig or greater than 2400 psig.

2.

The reactor shall not be critical (other than for the purposes of low power. physics tests) if the temperature of the reactor coolant is:

a.

less than Ill'F-plus the shif t in RTNDT at 1/4T (as determined in A.2.a.4), or

. ithin 40*F or less of the applicable heatup curve (as b.

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. determined in A.2.a.4), or 3.

The reactor shall not be critical without a ste.: Dubble in the pressurizer.

70

4..The reactor shall not be critical during inservice leak or hydrostatic testing of the reactor coolant system.

C.

Residual Heat Removal System 1

1.

The residual heat removal system (RHRS) must be isolated whenever the reactor coolant system pressure exceeds 600 psig or the temperature exceeds 450'F.

D.

Reactor Coolant System Low Temperature Overpressure Protection Whenever the reactor coolant system is less than the minimum pressurization temperature plus margin and the RCS is not vented:

1.

The reactor shall not be made critical.

2.

The RCPs may not be started (or " jogged") unless the pressurizer level is 1-ess than 80% and the steam generator temperature is less than 100*F above the RCS temperature.

3.4-2 Amendment tio. 3J, EE, E3, 114 i

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3.a.

If the pressurizer level ~ is 1.ess than-80%:

I Two power operated relief valves and their associated block:

valves shall be operable and set to prevent overpressure; 4

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One power' operated relief valve and its associated block valve, plus two RHR spring relief valves shall be operable p,

and set to prevent overpressure.

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b.

If the pressurizer level is greater than or equal to 80%,

the following valves shall be operable and set to prevent-overpressure:

Two PORVs and their associated block valves, and F

One RHR spring relief valve.

c.

Only one HPSI pump shall be aligned to provide charging flow and be available for HPSI service. Control switches for all the other HPSI pumps must be in the " pull-to-lock" position.

Exceotion: A second HPSI pump may be out of the

" pull-to-lock" position for up to 5 minutes for the purpose of rotating operating equipment.

-d.

At RCS pressures of less than 375 psig, HPSI pump flow must be aligned only through the charging system flow restrictor.

Remedial Action:

If any of the above required conditions (3a thru d) are not met, within six hours perform one of the following:

1.

Restore.the required condition, or 1

2.

Station a dedicated operator to prevent RCS overpressurization and within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> place the plant in-a condition where low temperature overpressure protection is not required.

Basis:

The heatup and cooldown limit curves (Figures 3.4-4 through 3.4-9)

I correspond to various heatup and cooldown rates for both normal and hydrostatic test operations. Cooldown limits curves are provided only for the.1/4T crack since the 1/4T crack is always governing.

However heatup limit curves are provided for both the 1/4T crack and 3/4T crack since either can be governing depending on the Adjusted h

Reference Temperatures (ARTS) at the 1/4T and 3/4T locations.

Linear interpolation is permissible. The heatup and cooldown curves were a

prepared based on initial crack tip RTNDTs of zero (0) degrees fahrenheit for the reactor vessel, and include adjustments for possible errors in the pressure and temperature sensing instruments.

3.4-3 Anendment No.

?', U, E3, 114 l

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(Continued) l The reactor vessel materials opposite the core have been tested to i

Appendix G of 10CFR50 to determine their RTNDT. Reactor operation and resultant fast neutron (E greater than 1 Mev) irradiation will cause an increase in RTN As a result of irradiation tests of actual vessel materials,DT.and application of Regulatory Guide 1.99, Revision 2, the Adjusted Reference Temperature (ART) can be determined at the critical 1/4T and 3/4T locatiens from Figure 3.4-3.

i The actun) Adjusted Reference Temperature (ART) of the vessel material will be established periodically during operation by removing and evaluating, in accordance with ASTM E185-73, reactor vessel material irradiation surveillance specimens installed near the inside wall of the reactor vessel in the core area.

i The pressure-temperature limit lines shown on Figures 3.4-4 through 3.4-9 for normal operation and inservice leak / hydrostatic testing, l

as well as the limits on criticality have been provided to assure compliance with the requirements of Appendix G to 10CFR50.

The heatup limits obtained using the procedure described in Specification 3.4.A.2 andFigures3.4.4and3.4-7maynogMHH(t).

be applicable for cumulative thermal generation greater than 5.414 x 10 Use of heatup limits for higher comulative thermal generation may be nonconservative. Additional restrictions on minimum reactor coolant temperature may be required to assure conservative heatup limits.

The margin which is added to MPT ensures compliance by accounting for the transient influences of LTOP related heatup or cooldown boundary conditions superimposed on the RCS pressure boundary. The maximum NDTT for all reactor coolant system retaining materials, with the pressure exception of the reactor pressure vessel, has been determined to be 40'F.

The Lowest Service Temperature limit line shown on Figure 3.4-1 is based upon this NDTT since Article NB-2322 (Summer Addenda of 1972) of.5ection III of the ASME Boiler and Pressure Vessel Code, requires the Lowest Service Temperature to be RTNDT + 100'F for piping, pumps and valves.

In addition, a 60'F margin is added to this for conservatism.

Below this temperature, the system pressure must be limited to a maximum of 25% of this system's design pressure of 2485 psig (20% of the e

preoperational hydro-test pressure of 3125 psig).

The minimum boltup temperature is established to comply with the manufacturer's specification for tensioning the reactor pressure vessel head.

The temperature provided in Table 3.4 1 corresponds to the measured 20'F NDTT of the teattor pressure vessel flange, which is not subject to radiation damage, plus 60'F data scatter in NDT measurements.

No correction for instrumentation error is included in the limit in Figure 3.4-1 since an adequate degree of conservatism is already applied 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 fatigue analysis performed in accordance with the ASME Code requirements.

3.4-4 Amendment No. 37, BE, 83, 114

V o-Remedial Action 2 to Specification D.3 requires stationing a dedicated operator. This operator shall be stationed at the main control board and protect against RCS overpressurization.

The PORVs in the variable pressure setpoint relief (VPSR) mode, in combination with the RHR safety valves when the pressurizer level exceeds 80%, constitute the Lt0P pressure relief system.

The charging system flow restrictor provides additional LTOP protection from an inadvertent HPSI pump injection transient. Use of this system provides_ protection of the 10 CFR 50 Appendix G limits when operating at lov temperatures.

4 4

3.4-5 Amendment No. 31, 65, 116 i

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TABLE 3.4.1

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LIMITS OF OPERATION FOR THE REACTOR CODLANT SYSTEM STEAM GENERATOR Limit Reactor Vessel Pressurizer Primary Side Secondary Side L

Maxi;um Heatup Rate (Of in any one-hour period) 100 100 100 l'

Maximum Cooldown Rate 100 200 100 (Of in any one-hour period)

Lo;;est Service Temperature 200 70 70 100 l

Maximum Pressure Below 621 500 500 230 Lo:est Service Temperature l

Minimum Boltup Temperature (*F) 80 Maxi:um Temperature Differente 340 Betreen Operating Loops and Pressurizer ('F) 1 i

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