ML20211B484

Proposed Tech Specs to Permit Complete Core off-loading of Source Range Monitors During First Refueling Outage

ML20211B484
Person / Time
Site:	Limerick
Issue date:	02/11/1987
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20211B412	List: ML20211B407 ML20211B449 ML20211B484
References
NUDOCS 8702190425
Download: ML20211B484 (7)

Text

- _ _ _ _ _ _ _

TABLE 3.3.6-1 (Continued)

CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION ACTION STATEMENTS 1

ACTION 60 Declare the RBM inoperable and take the ACTION required by Specification 3.1.4.3.

With the number of OPERABLE channels one or more less ACTION 61 than required by the Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within one hour.

ACTION 62 With number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channei in the tripped condition within one hour.

With the number of OPERABLE channels less than required ACTION 63 by the Minimum OPERABLE Channels per Trip Function requirement, initiate a rod block.

NOTES With THERMAL POWER > 30% of RATED THERMAL POWER.

With more than one control rod withdrawn.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

These channels are not required when sixteen or fewer fuel assemblies, adjacent to the SRMs, are in the core.

(a)

The RBM shall be automatically bypassed when a peripheral control rod is selected or the reference APRM channel indicates less than 30% of RATED THERMAL POWER.

(b)

This function shall be automatically bypassed if detector count rate is > 100 cps or the IRM channels are on range 3 or higher.

(c)

This function is automatically bypassed when the associated IRM channels are on range 8 or higher.

(d)

This function is automatically bypassed when the IRM channels are on range 3 or higher.

(e)

This function is automatically bypassed when the IRM channels are on range 1.

LIMERICK - UNIT 1 3/4 3-59 8702190425 070211 DR ADOCK 05000352 PDR

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3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 REACTOR MODE SWITCH Locking the OPERABLE reactor mode switch in the Shutdown or Refuel position, as specified, ensures that the restrictions on control rod withdrawal and refueling platform movement during the refueling operations are properly activated.

These conditions reinforce the refueling procedures and reduce the probability of inadvertent criticality, damage to reactor internals or fuel assemblies, and exposure e

of personnel to excessive radioactivity.

3/4.9.2 INSTRUMENTATION The OPERABILITY of at least two source range monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.

The minimum count rate is not required when sixteen or fewer fuel assemblies are in the core.

During a typical core reloading, two, three or four irradiated fuel assemblies will be loaded adjacent to each SRM to produce greater than the minimum required count rate.

Loading sequences are selected to provide for a continuous multiplying medium to be established between the required operable SRMs and the location of the core alteration.

This enhances the ability of the SRMs to respond to the loading of each fuel assembly.

During a core unloading, the last fuel to be removed is that fuel adjacent to the SRMs.

3/4.9.3 CONTROL ROD POSITION The requirement that all control rods be inserted during other CORE ALTERATIONS ensures that fuel will not be loaded into a cell without a control rod.

3/4.9.4 DECAY TIME The minimum requirement for reactor suberiticality prior to fuel movement ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products.

This decay time is consistent with the assumptions used in the accident analyses.

3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during movement of fuel within the reactor pressure vessel.

LIMERICK - UNIT 1 B 3/4 9-1

TABLE 3.3.6-1 CONTROL ROD HLOCM INSTRUMENTATION MINIMUM APPLICABLE OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION PER TRIP FUNCTION CONDITIONS ACTION (a) 1 ROD BLOtot asON! TOR s.

Upscale 2

1*

60 y

b.

Inoperative 2

t*

60 c.

Downscale 2

to 60 2.

APRM a.

Flow Biased Neutron Flus -

Upscale 4

i si b.

Inoperative 4

1.2.5 61 c.

Downscale 4

1 61 d.

Neutron Flum - Upscale. Startup 4

2.5 61 3.

SOURCE RANGE MONITORS ***

(b) a.

Oetector not full-in 3

2 61 2

5 61 (c) b.

Upscale 3

2 61 2

5 61 W

(c) c.

Inoperative 3

2 61 y

2 5

61 L3 (d) h d.

Downscale 2

5 61 m

4 INTERMEDIATE RANGE MONITORS a.

Detector not full-in 6

2.5 61 b.

Upscale 6

2.5 61 c.

Inoperative 6

2.5 61 (e) d.

Downscale 6

2.5 61 5.

SCRAM _ DISCHARGE VOLUME a.

water Level-High 2

1,2,5**

E2 6.

REACTOR COOLANT SYSTEM RECTRCULATION FLOW a.

Upscale 2

1 62 n.

Inoperative 2

1 62

(.

Comparator 2

1 62 7.

REAETOR MODE SWITCH SHUTDOWN POSITION 2

3.4 63

• See 3/4 3-59

• • See 3/4 3-59

• • • See 3/4 3-59 I

l

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REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) b.

Performance of a CHANNEL FUNCTIONAL TEST:

1. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the start of CORE ALTERATIONS, and

2. At least once per 7 days.

c.

Verifying that the channel count rate is at least 3.0 cps:*

1. Prior to control rod withdrawal, c

2. Prior to and 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 CORE ALTERATIONS, and

3. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

d.

Verifying, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to and 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, that the RPS circuitry " shorting links" have been removed during:

1. The time any control rod is withdrawn,** or

2. Shutdown margin demonstration.

• May be reduced to 0.7 cps provided the signal-to-noise ratio is > 2.

These channels are not required when sixteen or fewer fuel assemblies, adjacent to the SRMs, are in the core.

• • Not required for control rods removed per Specification 3.9.10.1 i

or 3.9.10.2.

l l

l LIMERICK - UNIT 1 3/4 9-4 i

i l

llMMMAGWIOl3MM@l&3 3/4.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 At least two source range monitor (SRM) channels

• shall be l

OPERABLE and inserted to the normal operating level with:

a.

Continuous visual indication in the control room, b.

At least one with audible alarm in the control room, c.

One of the required SRM detectors located in the quadrant where CORE ALTERATIONS are being performed and the other required SRM detector located in an adjacent quadrant, and d.

Unless adequate shutdown margin has been demonstrated, the shorting links shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn.**

APPLICABILITY:

OPERATIONAL CONDITION 5.

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS and insert all insertable control rods.

SURVEILLANCE REQUIREMENTS 4.9.2 Each of the above required SRM channels shall be demonstrated OPERABLE by:

a.

At least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s:

1. Performance of a CRANNEL CHECK,

2. Verifying the detectors are inserted to the normal operating level, and

3. During CORE ALTERATIONS, verifying that the detector of an OPERABLE SRM channel is located in the core quadrant where CORE ALTERATIONS are being performed and another is located in an adjacent quadrant.

• These channels are not required when sixteen or fewer fuel assemblies, adjacent to the SRMs, are in the core.

The use of special movable detectors during CORE ALTERATIONS in place of the normal SRM nuclear detectors is permissible as long as these special detectors are connected to the normal SRM circuits.

• • Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.

LIMERICK - UNIT 1 3/4 9-3 s

3 I

UNITED STATES OF AMERICA NUCLEAR REGULATORY C0 MISSION Before the Atomic Safety and Licensing Board 1

k In the Matter of Docket No. 50-352 I'

PHILADELPHIA ELECTRIC COMPANY t

(Limerick Generating Station, Unit No. 1)

CERTIFICATE OF SERVICE j

I hereby certify that copies of Philadelphia Electric Company's

]

Application for Amendment of Facility Operating License NPF-39 in the above-captioned matter were served on.the following by deposit in the United States mail, first-class postage prepaid on this lith day of February,1987.

Kathryn S. Lewis, Esquire Atomic Safety 6 Licensing Municipal Services Building Appeal Board Panel 15th 4 JFK Blvd.

U. S. Nuclear Regulatory Commission Philadelphia, PA 19107 Washington, D.C.

20555 6

Benjamin H. Vogler, Esquire Robert J. Sugarman, Esquire Counsel for NRC Staff Sugarman 6 Hellegers Office of the Executive Legal Director 16th Floor, City Place U. S. Nuclear Regulatory Commission 101 North Broad Street Washington, D.C.

20555 Philadelphia, PA' 19107 Angus R. Love, Esquire Troy B. Conner, Jr., Esquire Montgomery County Legal Aid Conner 4 Wetterhahn, P.C.

107 E. Main Street 1747 Pennsylvania Avenue, NW Norristown, PA 19401 Washington, D.C.

20006 Docket 4 Service Section Mr. Robert L. Anthony

.U. S. Nuclear Regulatory Commission 103 Vernon Lane, Box 186 Washington, D.C.

20555 - (3 copies)

Moylan, PA 19065 Atomic Safety 4 Licensing Board Panel Mr. Frank R. Romano U.-S. Nuclear Regulatory Commission 61 Forest Avenue Washington, D.C.

20555 Ambler, PA 19002 Barry M. Hartman, Esquire Timothy R. S. Campbell, Director Office of General Counsel Department of Emergency Services P.O. Box 11775 14 East Biddle Street Harrisburg, PA 17108 West Chester, PA 19380 i

A

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David Wersan, Esquire Ms. Maureen Mulligan Assistant Consumer Advocate Limerick Ecology Action Office of Consumer Advocate P.O. Box 761 l_

1425 Strawberry Square 762 Queen Street Harrisburg, PA 17120 Pottstown, PA 19464 j

Mr. Thomas Gerusky, Director Charles W. Elliott, Esquire

- Bureau of Radiation Protection Counsel for Limerick Ecology Action 325 N. 10th Street Department of Environmental Resources Fulton Bank Building, 5th Floor Easton, PA 18042 Third 6 Locust Streets Harrisburg, PA 17120 E. M. Kelly Senior Resident Inspector Spence W. Perry, Esquire U. S. Nuclear Regulatory Commission General Counsel P.O. Box 47 FEMA, Room 840 Sanatoga, PA 19464 500 C Street, SW Washington,- D.C.

20472 Regional Administrator U. S. Nuclear Regulatory Commission Director Region I 4

631 Park Avenue Pennsylvania Emergency l

Management Agency King of Prussia, PA 19406 Basement, Transportation 4 l

. Safety Building Harrisburg, PA 17120 Jay M. Gutierrez, Esquire U. S. Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, PA 19406 i

7 p ( Y,

'y Eugene,J. Bradley /

Attorney for

/

Philadelphia Electric Company s

2301 Market Street Philadelphia, PA 19101 e

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