ML20065U407

Amend 11 to License DPR-22,changing Tech Specs to Incorporate Revised Operating Limits Associated W/Mods to Scram Discharge Vol for Improved Hydraulic Coupling

ML20065U407
Person / Time
Site:	Monticello
Issue date:	10/08/1982
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Northern States Power Co
Shared Package
ML20065U409	List: ML20065U407 ML20065U410 ML20065U414
References
DPR-22-A-011 NUDOCS 8211040459
Download: ML20065U407 (9)

Text

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UNITED 8TATES g

NUCLEAR REGULATORY COMMISSION L

E WASHWGTON,0. C. 20566

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NORTHERN STATES POWER COMPANY

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DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendrirent No. 11 License No. DPR-22 1.

The Nuclear Re9ulatory Comission (the Comission) has found that:

A.

The applications for a'mendment by Northern States Power Company (the licensee) dated July 12, 1982 and September 17, 1982 and sup-piemented by letters dated September 7 and 23,1982 comply 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 Comission; 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to.the comon defense and security or to the health an4 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.

2.

Accordingly, the amendment authorizes the renoval of interim conditions to Facility Operating License No. DPR-22 that were implemented by the Comission's Order of January 9,1981. The license is further amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.2 is hereby amended to read as follows:

2.

Technical Specifications The Technical Specifications contained in Appendices A and B as revised through Amendment No. 11 are hereby incorporated in the license. The licensee shall o'perate the facility in accordance with the Technical Specifications.

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

FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: October 8, 1982 1

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o ATTACHMENT TO LICENSE AMENDMENT NO.11 FACILITY OPERATING LICENSE NO. DPR-22 DOCh'IT NO.'50-263 Remove the following pages and insert identically numbered pages:

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TABl.E 3.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT REQUIREMENTS

<j Hodes in which func-Total No. of Hin. No. of Operable j

tion must be Ope r-Instrument or Operating Instru-j l.imiting able or Operating **

Channels per ment Channels Per Required j

Trip Function Trip Settings Refuel (3) Startup Run Trip System Trip System (l)

Condition j

1.

Mode Switch in j

Shutdown X

X X

1 1.

A 1

j 2.

Manual Scram X

X X

l 1

A I

3.

Neutron Flux IRH d 120/125

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(See Note 2) of fulI scale X

X X(c)

.4 3

A

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a.

liigh-liigh b.

Inoperative 1

4.

Flow Referenced See Specifi-

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Neutron Flux APRM cations j

(See Note 5) 2.3A.!

X 3

2 A or B

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a. liigh-liigh j

b. Inope ra tive

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c. Downscale E 3/125 of,

full scale 5.

liigh Reactor 6 1075 psig X

X(f)

X(f) 2 2

A "l

Pressure j

6.

liigh Drywell Pressure 6 2 psig X(4)

X(e, f) X(e, f) 2 2

A 1

7.

Reactor Low Water I.evel 2 7'in.(6)

X X(f)

X(f) 2 2

A j

8.

Scram Discharge Volume liigh I.evel

a. East 6 56 gal.(8)

X(a)

X(f)

X(f) 2 2

A' l

b. West 656 gal.(8)

X(a)

X( f)

X( f) 2 2

A l

9.

Turbine Condenser j

Low Vacuum 3:23 in. Ilg X(b)

X(b.f) X(f) 2 2

A or C j

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..j 3.1/4.1 28 Amendment No. Il l

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Table 3.1.1 - Continued l

4

6. Seven inches on the water level instrumentation is 10'6" above the top of the active fuel at' rated power.

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7. Trips upon loss of oil pressure to the acceleration relay.

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8. 1.imited trip setting refers to the volume of water in the discharge volume receiver tank and does not include the volume in the lines to the level switches.

-_R_ equi re_d con _d_i_t ions _ when_ minimum cond,i t ions _ for opera t ion a re. not satisfind.

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A.

All operable control rods fully inserted within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

.i B.

Power on IRM range or below and reactor in Startup, Refuel, or Shutdown mode.

C.

Reactor in Startup or Refuel mode and pressure below 600 psig.

4 D.

. Reactor power less than 4 5% (7 51. 5 MW t. ).

J

• • Allowable Rypass Conditions

.1 It is permissible to bypass:

The scram discharge volume liigh Water Level scram function in the refuel mode to allow reae, tor protection a.

system reset. A rod block shall be applied while the hypass is in effect.

j b.

The 1.ow Condenser vacuum and MSIV closure scram functions. in the Refuel and Startup modes if reactor pressure j

is below 600 peig.

c.

The scram function of an IRM instrument channel when the reactor is in the Run mode and the associated APRM is operable and indicating at least 3/125 full scale.

1 The turbine stop valve closure and fast control valve closure scram functions when the reactor thermal power d.

a' is f45%(751.5 MWt).

i.

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3.1/4.1 30

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Amendment No.

11 3

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SCRAM INSTRUMEN1.. IBRATION l

MINIMUM CALIBRATION FREQUENCES FOR REACTOR PROTECTION INSTRUMENT CHANNELS

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INSTRUMENT CHANNEL CROUP CALIBRATION METHOD MINIMUM FREQUENCY (2)

APRM E

Heat Ratance Once every 3 days (4) 1RM E

Ileat Balance See Note 1 l}

High Reactor Pressure D

Pressure Standard Every 3 months

1

1 High Drywell Pressure D

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Pressure Standard Every 3 months

i Ij Low Reactor Water D

Pressure Standard Every 3 months High Water Level in Scram Discharge D or E Water Level

• • Every 3 months f

t Condenser Low Vacuum D

Vacuum Standard Every 3 months q

High Stess Line Radiation E

See Note 3 See Note 3 4

Main Steamline Isolation Valve Closure D

Observation Every Operating Cycle

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Turbine Control Valve Fast Closure D

Pressure Standard Every 3 months D

Obse rvation Every. Operating Cycle Turbine Stop Valve Closure 1;

Recirculation Flow Meters &

Pressure Staniard Every 3 months Flow Instrumentation t

4, Notes:

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1.

Perform calibration test durlag every startup and normal, shutdoen.

f 2.

Calibration tests are not required when the systems are not required to be operable or are tripped' If tests are missed, they shall be performed prior to returning the systems to an operable. status.

3.

This instrument will be calibrated every three months by means of a build-in current source, and each refueling outage with a known radioactive source.

4.

This calibration is performed by taking a heat balance and adjus' ting the APRM to agree with the heat balance. Alarms and trips will be verified and calibrated if necessary during weekly functional test.

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D.

Passive type devices.

E.

Vacuum tube or semiconductor devices and detectors that drif t or lose senritivity.

3. 1/4.1 Amendment No. 3 I

Amendment No. Il i

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Bases Continued:

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3.1 Three APRH instrument channels are provided for each protection trip system. APRM's #1 and #3 operate contacts in one subchannel, and APRM's #2 and #3 operate contacts in the other subchannel.

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APRH's #4,#5, and #6 are arranged similarly in the other protection trip system.

Each protection f

F trip system has one more APRM than is necessary to meet the minimum number required. This allows the bypassing of one APRH per protection trip system for maintenance, testing, or calibration.

Ad-E ditional IRH channels have also been provided to allow for hypassing of one such channel in each g

trip system.

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The loses for the scram set tings for the IRM, APRM, high reactor pressure, reactor low water level, s

turbine control valve fast closure, and turbine stop valve closure are discussed in Specifications j

2.3 and 2.4.

.j Instrumentation (pressure switches) in the drywell are provided to detect a loss of'toolant accident I

and initiate the emergency core cooling equipment. This instrumentation is a backup to the water level instrunentation which is discussed in Specification '3.2.

The control rod drive scram system is designed so that all'of the water which is discharged from the a

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reactor by the scram can be accommodated in the discharge piping. Part of this piping consists of two.

instrument volumes which accommodate in excess of 56 gallons of water each and is the low point in the j

piping. During normal operation the discharge volumes are empty; however, should they fill with-water, i

the

• water discharge to the piping from the reactor could not be accommodated which would result in slow scram times or partial or no control rod insertion. To preclude this occurrence, level switches have been provided in the instrument volunes which alarm and sciam the reactor when the volume of water in either of the discharge volume receiver tanks reaches 56 gallons. At this point there is sufficient volume in the piping to accommodate the scram without impairment of the scram times or amount of insertion of the control rods. This function shuts the reactor down while suf ficient voltune remains to accommodate the discharged water and precludes the situation in which a scram would be required but not be able to perform its function adequately.

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Loss of condenser vacuum occurs when.the condenser can no longer handle the heat in;.u t. Loss of e

3.1 BASES 36 k

s 3

Amendment No. 11 s

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Table 3.2.3 - Continued Instrumentation That Initiates Rod Block 1

Reactor Modes in Which Min. No. o f Ope r-Function Must Be Operable Total No. of able or Operating

,j or Ope' rating and Allow-Instrument Instrument Channels j

able Bypass Conditions **

Channels per Per Trip' System Required Function Trip Settings Refuel Startup Run Trip system (Notes 1,6)

Conditions

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44 RBM I

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a. Upscale 5 0.f>5 W 43 X(c)

I 1 (Note 5)

D or E I

3 (flow ref-(Note 2) l crenced).

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b. Downscale 23/125 full X(c) 1 I (Note D or E l

5. Scram Dischnrge Volume

,j Water Level -

i liigh

a. East i.40 gal.

X X

1 1

B and D, or A i

l

b. West.

1 40 gal.

X X

1 1

B and D, or A

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l Notes:

J (1)

There shall be two operable or operating trip systems for each function.

l( the minimum number of i

operable or operating instrument channels cannot be met for one of the two trip systems, this condition may exist up to seven days provided that during this time.-the operable system is functionally tested 1

immediately and daily thereafter. This note is not applicable to the Scram Discharge Volume Rod Block since it exists in only one trip system.

(2)

"W" is the reactor recirculation driving flow in percent.

I l

(3)

Only one of the four SRM channels may be bypassed.

(4)

There must be at least one operable or operating IRM channel monitoring each core quadrant.

(5)

One of the two RBM's may be bypassed for maintenance and/or testing for periods not in excess of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 30 day period. An RBM channel will be considered inoperable if there are less than half the total number of normat inputs from any LPRM level.

3.2/4.2 57

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Amendment No. Il a

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i 3.0 I.IMITING CONDITIONS FOR OPERATION 4.0 SllRVEII.I.ANCE R EQtil REMEfft'S i

Any four rod group may contain a control rod which is valved

[

out of service provided the above requirements and Specifica-t ion 3. 3. A a re me t.

3.

If the cycle average scram insertion time ( % ), based on the de-energization of the scram pilot valve solenoids at time zero, I

of all operable control rods in the reactor power operation condition at the 20% inserted position is larger than the l

adjustel analysis mean scram time ('fe

), a more restrict ive MCPR limit (see section 3.II.C.1) shall be used.

D.

Control Rod Accumulators D.

Control Rod Accumulators t

In the "Startup" or "Run" Mode, a rod accumulator may be inope rab le Once a ' shift' check the status l

provided that no other control rod in the nine-rod square array in the cont rol room of the j

around this rod has a:

required Operable accumulator pressure and level' alarms.

~

1.

Inoperable accumulator.

a 2.

Directional control valve electrically disarmed while in a.

i non-fully inserted position.

y,\\ t, If a control rod with an inoperable accumulator is inserted l

" full-in" and its directional ' control valves are electrically i (S disarmed, it shall not he considered to have an inoperable

=

l accumulator.

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In the " Refuel" Mode, the accumulator associated with any i

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withdrawn control rod must be Operable unless all the fuel has been, removed from the cell containing-that control rod.

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i.3/4.3 82 1

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Amendment l'No. 5, 11

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