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Proposed Tech Specs Reflecting Editorial & Administrative Corrections to Provide Clarification & Consistency
	ML20154P219
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	09/21/1988
From:	; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	;
Shared Package
ML20154P214	List: ML20154P211; ML20154P219;
References
	NUDOCS 8809300158
	Download: ML20154P219 (7)
	v • d • e

7.

1 ATTACletENT Consumers Power Company B! Rock Point Plant Docket 50-155 e

PROPOSED TEClei! CAL SPECIFICATION PACE CHANCES September 21, 1948 i

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6 Pages OC0848-0102-NLO2 8809300158 880921 PDR ADOCK 05000155 p

PDC

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18 4.1.2 (Contd) is above 300 psig. The shutdown cooling system shall be OPERABLE

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and ready for service during REFUELINC OPERATIONS and the breakers

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for MO-7070 and MO-7071 shall be tagged "open".

The primary coolant shall be sampled and analysed daily during periods of POWER

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OPERATION. The following are absolute limits which if exceeded

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shall necessitate reactor SHUTDOWW. Corrective action will

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necessarily be taken at more stringent limits to minimise the possibility of these absolute limits ever being reached.

Conductivity (Micronho/ca)

Maximum 5

Maximum Transient

10 pH (Lower and Upper L) 4.0 and 10.0 Chloride Ion (Ppa) 1.0 Boron (Ppa) 100 Isotopic analysis of the primary coolant to determine the DOSE

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EQUIVALENT I-131 concentration shall be performed at least every

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72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during periods of operation.

1.

If the DOSE EQUIVALENT I-131 concentration exceeds 0.2 pCi/al

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and is less than or equal to 4.0 -pC1/st e, isotopic analysis to

-. determine. DOSE EQUIVALENT I-131 shall.be performed every 24

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hours until the activity is less than 0.2 pC1/al.

2.

If the DOSE EQUIVALENT I-131 exceeds 4.0 pci/m1, the plant

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shall be placed in a SHUTDOWW condition with the main steam

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isolation valve closed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

(c) Leakane Limits.

1.

If the primary coolant system leakage exceeds 1 spa and the source of leakage is not identified, the reactor shall be SKUTDOWW as described in Section 1.2.5(a) within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,

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and cooldown to a COLD SHUTDOWW condition shall be initiated

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within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.

If leakage from the primary coolant system escoeds 10 spa, the

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reactor shall be SHVfDOWW as described in Section 1.2.5(a)

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within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and cooldown to a COLD SKUTDOWW condition

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shall be initiated within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.(t iLETED)

Conductivity is expected to increase temporarily af ter startups from cold shutdown. The maximum transient value here stated is the masimum permissible and applies only to the period subsequent to a cold shutdown between criticality and 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after reaching 201 rated power.

/ Proposed

// Proposed by CR of 7/23/87 OC0868-0102-NL02

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1 30 5.1.3 (Contd>

(a) Accumulator Pressure - Each of the 32 accumulators shall supply stored energy in the form of water under nitrogen pressure for scramming control rod drives. The minimum

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gas volume in each accumulator, during POWgR OPERATION,

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shall be 600 cubic inches.

(b) seactor Pressure - Reactor pressure, if above 450 pois, shall supply energy for scramming control rod drives if

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l accumulator pressure falls below reactor pressure.

The control rod drives shall be mounted on the bottom of the reactor vessel and attached to the bottom of the poison section with a coupling. The half coupling, attached to the control rod drive, shall consist of sin finger-like segments which fore a ho110w spheroid. The other half coupling shall be an integral part of the poison section. The force required to engage the coupling shall be approximately 60 pound s.

Once engaged, the coupling can be disengaged only by the deliberate movement of an unlocking mechanise. Control and instrumentation shall be provided to enable the operator to make a coupitng integrity chesk.

Positten. indication at each locking position.shall be provided by stationary magnetic switches actuated by a permanent magnet in the movable drive piston. Drive position indication shall be displayed in the cJntrol room by a digital readout system.

The center tube of the drive mechanism is a well containing the position indicator probe. This area is at atmospheric pressure. The probe mounts a series of hermetically sealed, magnetically operated switches, each of which indicates a discrete rod position. The switches are operated by a peimanent magnet carried by the drive piston. The intervening walls are of nommagnetic meterial, allowing each switch to be operated as the piston passes. Estra switches are provided at each end of the stroke to indicate limits.

A thermecouple is placed at the top of the position indicator probe of each control rod drive and is held in position by spring clips. The temperature readings f rom these thereocouples provide an indication of the seal operating conditions and detection of flow froe reactor to scram dump tank (via leaking screa valve).

Control rod drive features shall be as follows:

Type Locking Piston Normal Stroke Length, Inches 64.0 Proposed OC0844-0102-ML42 L,

F 47 5.2.2 control Rod tystas (Contd) rods. Evaluation of this requirement shall be based on previous esperimental measurements.

(g) Minimus Accuracy of Rod position Indicating System the control rod drive positions itself in 23 discrete i

positions over its travel. The position indicating tystem I

is of a digital readout design and indicates the drive position over a range of 1.5 inches for each position of the l

drive. Control rods shall not be allowed to remain in position where the indication is not operable.

If all indication for a particular control rod is lost, the rod shall not be moved until the indication has been restored, escept for screa.

(h) Oseration of the Seran Dump Tank Valves and Ninh 1,evel Alare Ttt scram dump tank air operated vent and drain valves

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sh.11 be (1) verified open at least once per 31 days, and (2) cycled through at least one complete cycle of full travel once per quarter. These velves may be closed

.. incereittently for testinrunder adminletrative controls.

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At every refueling, outage, the valves shall be tested to

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close within 20 seconds of receipt of a scraa signal and the j

scram dump tank high level alare shall be verified operable l

at a level of 10 2 1/2 inch below the tank centerline. An

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unexplained high level alare shall require immediate investigation and if not corrected, subsequent insertion of all or all but one control rod drive within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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5.2.3 Lieuld Poison System The liquid poison system shall be available for operation at all times during refueling and power operation. The reactor shall be shutdown in any situation where the poison solution tank level l

drops below and equivalent of 850 sations 19 weight percent sodium pentaborate or where the poisen solutten storage temperature drops to less than 5'F above saturation temperature. The maaimun l

allowable concentration shall be 30 weight percent of sedive pentaborate. The minimum worth of the liquid poison systen l

(based on normal water level) shall be 251 s gg/hef t.

Component s

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of the system shan be checked at one to two month untervale for proper operation escept for actuation of the lajection valves.

I The liquid poleon system shall be used at any tiae when subcriticality cannot be assured by the normal shutdown mechantes. Injection shall be continued until a minime shutdown margin of 0.01 n gg/kegg is assured in the most reacti te core.

e The reactor shall not be operated af ter poison has been injected until the boron I

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/ proposed

// proposed by CR of 12/30/86 i

OC0848-0102-Nt.02 I

72 7.3.2 (Contd)

(e) Critical approaches shall be monitored using source range monitors. The start-up rate shall be restricted to demoni.trate that the

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about10'goverrangemonitorsoverlapthesourcerangemonitorsat

% indicated full poser on the power range monitor is

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normal and satisf actory for control and safety piirposes before continuing further into the power range. Control rod withdrawal sequence shall be speciflod and limited to those sequences shown by previous analysis or tests to preserve fuel integrity in the event of accidental reactivity insertion either while starting up or at power.

(f) The power shall be adjusted once criticality is reached to maintain a reactor vesssi temperature rise rate not to exceed 100'F per hour.

l (g) The turbine shaft sealing system shall be placed in service as soon as sufficient steam pressure is available (approximately l

150 pais).

(h) The condenser shall be evacuated with the mechanical vacuum pump and the air ejector vill be placed in service.

(1) Turbine heating shall be started during this operation sequence.

i After turbine heating is completed, the turbine shall be I

gradually brought up to speed.

l (j) The mode of turbine control shall be transferred to the initial pressure regulator.

(k) The control rods shall be adjusted to provide the desired power distribution within the core.

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7.3.3 He t S t ar t-t'p l

Uhenever the plant has been shut down for a period of time with the reactor vessel and auxiliaries remaining pressurized, a hot start-up procedure shall be followed to return the plant to service. This procedure vill be essentially independent of the cause of shutdevn assuming that the cause is recognized and any nonstandard conditions have been corrected. The reactor instrumentation shall be Teset and downscaled and a hot start-up checklist shall be completed prior to the withdraval of control rods.

A coupling integrity check shall be made in accordance with Section 5.2.2(d).

The start-up ahall then proceed in accordance with Paragraphs (d) through (k) of Section 7.3.2 of the normal cold start-up procedure outlined above.

I Proposed OC0888-0102-NLO2

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s 75 7.4 (Contd)

(e) The 11guld poison system shall be evallable and ready for use.

(f) Containment sphere integrity provisions shall be in effect during REFUELIWC OPERATIONS.

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(3) Unitradiated fuel shall normally be stored in air in a new fuel storage area within the containment sphere.

(h) Irradiated fuel and irradiated channels shall be stared in the spent fuel storage pool.

(1) The minimum refueling crew during RgrVELINC OPERATIONg shall

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be f ou r men. There shall be a licensed operator in the control room at all times, and the Shif t Supervisor shall be in charge.

t (j) Functional testing of the trip mechanism of the fuel transfer cask safety catch device shall be performed prior to

.. commencing-refueling activities.

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7.$, 7.5.1 - 7.5.6 Deleted (Change 46, 12/19/75) 7.5.7 It shall be permissible to temove a control rod drive from the reactor vessel when the reactor is in the SHUTDOWW condition and

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l the mode selector switch is locked in the "Shutdown" position.

The core shutdown margin at 0.31 ok,(g/keff with the strongest

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l control rod out of the core shall have been met prior to the control rod drive removall and in addition, the equipment shall he properly tagged.

The control rod drivs that was removed shall without delay be replaced by a spare control rod drive or the original control rod drive shall be reinstalled. One control rod drive pump shall be operating during remeval and reinser:Lon and during the time the control rod drive is outside the reactor vesist.

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j 7.6 OPgRAT!0tiAL TESTINC OF WUCMAR SAFECUARDS SYSTEMS i

l procedures for testing of plant components and safety systeme I

which have a potential safeguards function are prescribed in l

Sections 3.0 through 6.0.

These tests and frequency of testing i

shall be as tabulated.

I pro po sed OC0 A44-0102-WLO2

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.e ACM!WISTRATIVE CONTROLS l

RESPONSIBILITIES (Continued) j.

Review of any accidental, unplanned or uncontrolled radioactive release including the preparation of reports covering evaluation, reco'weendations and disposition of the l

corrective action to prevent recurrence and the forwarding of these reports to the Plant Manager and to the Nuclear

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Safety Board (NSg).

l PRC review may be performed through a routing of the item subject to

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ho requirement s of Specification 6.5.1.7.

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AUTHORITY 6.5.1.7 The PRC shallt Recommend in writing to the Plant Manager approval or

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a.

disapproval of itses considered under Specifications 6.5.1.6.a through d. above.

b.

Render determinations in writing with regard to whether or not each ites considered under Specifications 6.5.1.6.a through e. above constitutes an anteviewd safety question.

e c.

Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Vice l

President - Nuclear Operations and to the Vice Chaitaan of I

WSg of any disagreement betwen the PRC and the Plant Managert however, the Plant Manager shall have responsibility

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for the resolution of such disagreements pursuant to Specification 6.1.1 above.

The PRC Chairman may recosamend to the Plant Manager approval of

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those items identified in Specifications 6.5.1.6 4.

through d. and 1.

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above based on a routing review provided the following conditions are mett (1) at least five PRC members, including the Chairman and no more than 2 alternates, shall review the item, concur with determination as to whether or not the ites constitutes an unreviewed saf ety question, and provide written cosuments on the itent (2) all comment s shall be resolved to the satisfaction of the reviewers providing the commentsi and (3) if the PRC Chairman determines that the comments are sigt.ificant, the ites (including cosaments and resolutions) shall be recirculated to all reviewers for additional comments.

1 The iten shall be reviewed at a PRC meeting in the event thatI i

(1) comments are net resolvedt or (2) the Plant Manager overrides

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the recommendations of the PRCl or (3) a proposed change to the Technical Specificacions involves a safety limit, a limiting safety

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i systes setting or a limiting condition for operations or (4) the item was a REPORTAgLE EVENT as defined in 10 CFR 50.73.

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/ Proposed

// Proposed by CR of 7/23/87 l

OC088 8-0102-NI.02

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ML20154P219

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