ML20151S048

Proposed Tech Specs Allowing Normal Movement of Local Power Range Monitor Not to Be Considered Core Alteration

ML20151S048
Person / Time
Site:	River Bend
Issue date:	08/05/1988
From:	GULF STATES UTILITIES CO.
To:
Shared Package
ML20151S043	List: ML20151S048 RBG-28400, Application for Amend to License NPF-47,allowing Normal Movement of Local Power Range Monitor Not to Be Considered Core Alteration.Fee Paid
References
NUDOCS 8808150041
Download: ML20151S048 (2)

Text

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DE~INITIONS The CHANNEL FUNCTIONAL TEST may be performeo by any series of sequential, overlapping or total channel steps such that the entire channel is tested.

- CORE ALTERATION

1. 7 CORE ALTERATION shall ,:e the addition, removal, relocation or movement of fuel, sources, incere instruments or reactivity controls within the reactor pressure vessel with the ve isel head removed and fuel in the vessel. Normal movement of the SRMs, IRMs,VTIPs or special movable detectors is not considered l a CORE ALTERATION. Susperision of CORE ALTERATIONS shall not preclude completion of the movement of a component to a safe conservative position.

CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY 1.8 The CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY (CMFLP9) shall be the highest value of the'FLP0 whicn exists in the core.

CRITICAL POWER RATIO 1.9 The CRITICAL POWER RATIO (CPR) shall be the ratio of that power in the assembly which is calculated by %'pplication of the GEXL correlation to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

DOSE EQUIVALENT I-131 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131, microcuries per gram, which alone would produce the same thyroid dose as. the quantity and isotopic mixture of I-131, I-132, ~ -133, I-134, and I-135 actually present.

The thyroid dose cor. version factors used for this calculation shall be those listed in Table III of TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites."

ORYWELL INTEGRITY 1.11 ORYWELL INTEGRITY shall exist v. hen:

a. All drywell penetrations required to be clused during accident conditions are either:

o) ud@8 1. Capable of being closed by an OPERABLE drywell automatic isola-

@@l tion system, or oo 8[$ 2. Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed position, except as pro- ,

-y vided in Specificatien 3.6.4.

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$4 b. All drywell equipment hatches are closed and sealed. ,

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@@@ c. The drywell airlock is in compliance with the requirements of j meta. Specification 3.6.2.3. .

RIVER BEND - UNIT 1 1-2

9 TABLE 3.3.1-1 (Ccntinued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION ACTION 1 -

Be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 2 -

Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, verify all insertable control rods to be inserted in the core and lock the reactor mode switch in the Shutdown -

position.

ACTION 3 -

Suspend all operations involving CORE ALTERATIONS **and insert all insertable control rods within one hour. l ACTION 4 -

Be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 5 -

Be in STARTUP with the main steam line isolation valves closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 6 -

Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, place the inoperable instrument channels in both trip systems in the tripped .cond'i.lon; otherwise, initiate a re-duction in THERMAL POWER within 15 minutet and reduce turbine first stage pressure to less than the automatic bypass setooint (less than 40% of RATED THERMAL' POWER) within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

ACTION 7 -

Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, verify all insertable control rods to be inserted.

ACTION 8 -

Lock the reactor mode switch in the Shutdown position within one h.our.

ACTION 9 -

Suspend all operations involving CORE ALTERATIONS *", and insert l all insertable control rods and lock the reactor acde switch in the Shutdown position within one hour.

ACTION 10 - Within one hour, place the inoperable instrument channels in both trip systems in the tripped condition; otherwise be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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";;;;pt rep'ec.;;n; ef LPRM etring;, provid:$-SRM in;tr;;;nt:ti:n i: 0"ERA"LE per Specificatien 0.0.2.-

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RIVER BEND - UNIT 1 3/4 3-4 I

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