ML20207Q035

Proposed Tech Spec Changes Re Main Steam Line Radiation Monitors & Steam Tunnel Ventilation Radiation Monitors

ML20207Q035
Person / Time
Site:	Millstone
Issue date:	12/16/1986
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20207Q033	List: B12339, Application for Amend to License DPR-21,revising Tech Specs by Changing Setpoints on Main Steam Line Radiation Monitors & Steam Tunnel Ventilation Radiation Monitors to Facilitate Implementation of Hydrogen Water Chemistry Test.Fee Paid ML20207Q035
References
NUDOCS 8701210143
Download: ML20207Q035 (7)

Text

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1 b.

TA8tE 3.1.1 (Continued)

REACTOR Pfl0TECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENTS 1

i j

Mint:un Number

{

of Optrable Modes in which Function Inst. Channels Trip Function Trip Level Setting Mest Be operable Action

• per Trip (1)

REFUEL /.

STARIUP/ HOT System SHUTOOWN (8,11)

STAM08Y RUN 2

Turbine Condenser Low 223 In. Hg. Vacuun X (3)

X (3)

X A or C Vacuum l

2 Main Steamilne Radiation 57 x Normal Full Power

~

X X

X A or C

]

Background (12) 4 (6)

Malm Steam 11ne Isolation

$10E Valve C.losure X (3)

X (3)

X A or C Valve Closure 2

Turbine Control Valve See Section 2.1.2 F X (4)

X (4)

X (4)

A or C j

Fast closure I

j 2

Turbine Stop Valve

$105 Valve Closure X (4)

X (4)

X (4)

A or C 4

Mstes:

1.

There shall be two operable or tripped trip systees for each function.

2.

Permissible to bypass, with control rod block, for reactor protection systee reset in REFUEL and SHUTOOWN positions of the reactor mode switch, i

' 3.

Bypassed when reactor pressure Is <600 psig.

4.

Bypassed when first stage turbine pressure is less than that which corresponds to 45% rated stese flow (generator output approxleately 307 MWe).

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8701210143 861216 PDR ADOCK 05000245 l

p PDR l

Millstone Unit 1 3/4 1-4

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i TA8LE 3.1.1 (Continued)

Reactor protection System (Scram) Instrumentation Requirements Motes:

I 5.

IRM's are bypassed when mode switch is placed in RUN. The detector for each operable IRM channel shall

]

be fully inserted until the associated APRM channel is operable and indicating at.least 3/125 full scale.****

6.

The design permits closure of any one valve without a scram being initiat.ed.

7.

May be bypassed when necessary by closing the manual instrument isolation valve for scram of PS-1621 A through 0 j

during purging for containment inerting or deinerting.

.1, 8.

When the reactor is suberitical and the reactor water temperature is less than 212*F, only the following trip functions need to be operable:

a a.

Mode Switch in SHUT 00WM b.

Manual Scram c.

High Flux IRM d.

Scram Olscharge Volume High Level i

e.

APRM Reduced High Flux 9

Not required to be operable when primary containment integrity is not required.

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10. With the mode switch in RUN position an inoperative trip function also requires an associated APRM "downscale alarm."

11. Trip functions are not required to be operable if all control rods are fully inserted, and either electrically or j

hydraulically disersed in accordance with Specification 4.1.0.

12. (See attached).

l

• Action: If the first column cannat be met for one of the trip systees, that trip system shall be tripped. If the first column i

cannot be met for both trip systems, the appropriate actions listed below shall be taken:

i l

A.

Initiate Insertion of operable rods and complete Insertion of all operable rods within four hours.

I B.

Reduce power. level to IRM range and place mode switch in the STARTUP/ HOT STAN08Y position within elght hours.

l C.

Reduce turbine load and close mein steam line isolation valves within eight hours.

l An APRM will be considered inoperable if there are less than two LPRM inputs per level or there are less than 50% of the normal compliment of LPRM's to an APlut.

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One Inch on the water level Instrumentation is 127 inches above the top of the active fuel.

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Millstone Unit 1 3/4 1-5

c22:

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power at greater than 20% rated power, the normal full power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test. n e background radiation level and associated trip' setpoints may be adjusted during the test program based en either calculations or measurements of actual radiation levels resulting from hydrogen injection. We background radiation level shall be determined

. and associated trip setpoints shall be set: within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of reestablishing normal radiation levels after completion of the test program, or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor power levels below 20% rated power.

If, due to a recirculation pump trip or other power reduction event, the reactor power drops below 20% rated power with the nst.m setpoints at their test value, control rod withdrawal will be prohibited until the necessary setpoint readjustment can be made.

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r 1

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s TABLE 3.2.1 i

1 I

INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION FUNCTIONS rfinimum Number of,

I Operable Instrument Channels Per Trip l

System (1)

Instruments Trip Level Setting Action (3) i 2

Reactor Low Water 2127 inches above top of active fuel A

j 2

Reactor Low Low Water 79 (+4-0) inches above top of active fuel A

2 (4)

High Orywell Pressure

$2 psig A

2 (2) (5)

High Flow Main Steamline 5120% of rated steam flow B

i 2 cf 4 in each of High Temperature Main j

2 subchannels Steamline Tunnel

$200*F B

j 2

High Radiation Main, j

steamline Tunnel (6).

57 times normal rated power background B

l l

2 Low Pressure Main 1825 psig B

Steamlines 2

High Flow Isolation 164 inches 2 trip setting (water differential C

l Condenst.c Line on steam line) 2150 inches.

44 inches 2 trip setting (water differential j

on water side) 235 inches.

(1r Whenever primary containment integrity is required, there shall.be two operable or tripped trip systems for each function, except for low pressure main steamline which only need be available in the RUN position.

(2) Per each steamline.

(3) Action:

If the first column cannot be met for one of the trip systems, that trip system shall be tripped.

If the first column cannot be met for both trip systems, the appropriate actions listed below shall be taken:

A.

Initiate an orderly shutdown and have reactor in cold shutdown condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

B.

Initiate an orderly load reduction and have reactor in HOT STANDBY within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

I C.

Close isolation valves in isolation condenser system.

(4) May be bypassed when necessary by closing the manual instrument isolation valve for PS-1621, A through D, during purging for containment inerting or deinerting.

(5) Minimum number of operable instrument channels per trip system requirement does not have to be met for a steamline if both containment isolation valves in the 11ne are closed.

~~

(6)

(See attached).,

Millstone Unit 1 3/4 2-2

~

a Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor powr at greater than 201 rated power, the norr.al full power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test. 'Ihe background radiation level and associated trip' setpoints may be adjusted during the test program based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. 'Ihe background radiation level shall be determined and associated trip setpoints shall be set: within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of

. reestablishing normal radiation levels after completion of the test program, or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor power levels below 20% rated power. If, due to a recirculation pump trip or other power reduction event, the reactor power drops below 20% rated power with the MSLRM setpoints at their test value, control rod withdrawal will be prohibited until the necessary setpoint readjustment can be made.

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LIMITING CCICITION IDR OPERATIm 1

3.2 PRCTIECTIVE INSDURWTATION C.2.

We minimum number of operable instrument channels specified in Table 3.2.3 for the Rod Block Monitor may be reduced by one for maintenance an&'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.

D.

Air Eiector Off-Gas System 1.

Except as specified in 3.2.D.2 below, both air ejector off-gas system radiation sonitors shall be operable during reactor power operation.

Se trip settings for the monitors shall be set at a value not to exceed the equivalent of the instantaneous stack release limit specified in Specification 3.8.

Se time delay setting for closure of the staan jet 4 1r ejector off-gas isolation valve shall not exceed

~

15 minutes.

2.

From and after the date that one of the two air ejector off-gas system radiation monitors is made or found to be inoperable, reactor power operation is permissible only during the succeeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, provided the inoperable motor is tripped, unless such system is sooner made operable.

)

E.

Reactor Building ventilation Isolation, steam Tunnel ventilation Isolation and Standby Gas Treatment System Initiation 1.

Except as specified in 3.2.E.2 below, six radiation monitors shall be operable at all times.

2.

One of the two radiation monitors in the reactor building ventilation duct, one of the two radiation sonitors on the refueling floor and one of the two radiation monitors in the steam tunnel ventilation may be inoperable for 24 hrs. If it is not restored to service in this time, the reactor building ventilation system and steam tunnel p,

ventilation system shall be isolated and the standby gas treatment

, operated until repairs are complete.

i 3.

Se radiation monitors shall be set to trip as follows:

a.

Ventilation dud - 11 ar/hr.

b.

Refueling floor - 100 ar/hr.

I Steam tunnel ventilation - 50 ar/hr.'* 8 i

c.

i

' 'g.<.

x c

.y Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test, the setpoint may be increased as necescary, up to 100 ar/hr, provided that the difference between the increased sei. point and the calculated value of*

l the background radiation level expected during the test does not exceed 50 mr/hr. We setpoint shall be returned to normal within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of reestablishing normal g

radiation levels after completion of the test program.

MILLSTONE LNIT - 1 3/4 2-12 i

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s 3.2 Fium;nVE INSTIGENIATION BASES

'IVO air ejector off-gas monitors are provided and when their trip point is reached, cause an isolation of the air ejector off-gas line. Isolation is initiated when both instruments reach their high trip point or one has an ~

upscale trip and the other a downscale trip. W ere is a 15-minute delay before, the air ejector off-gas isolation valve is closed. 21s delay is accounted for by the 30-minute holdup time of the off-gas before it is released to the stack.

Both instruments are required for trip but the instruments are so designed that any instrument failure gives a downscale trip. Se trip settings of the instruments are set so that any instrument failure gives a downscale trip. We trip settings of the instruments are set so that the instantancous stack release rate limit given in Specification 3.8 is not exceeded.

hree sets of two radiation monitors are provided which initiate isolation of the reactor building and steam tunnel ventilation and operation of the standby gas treatment system. One set of monitors is located in the reactor building ventilation exhaust duct, one set is located in the vicinity of the fuel pool, and the other set is located adjacent to the steam tunnel ventilation exhaust duct. A high level trip on any one of the six monitors or two downscale trips on any one set of monitors will initiate the standby gas treatment system and isolate the ventilation system. Trip settings of 100 ar/hr on the fuel pool monitor,11 ar/hr on the ventilation duct monitor, and 50 mr/hr on the steam tunnel ventilation monitor are based on initiating normal ventilation isolation and standby gas treatment system operation.

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MILLSTONE UNIT - 1 B 3/4 2-5

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