Text

Amended TS Pages Reactivity Control Systems, Power Distribution Limits, and Special Test Exceptions
	ML032691386
Person / Time
Site:	Millstone
Issue date:	09/17/2003
From:	; NRC/NRR/DLPM
To:	;
References
	TAC MB6108
	Download: ML032691386 (45)
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V INDEX LIMITING CONDITIONS FOR OPERATION AND SURVILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY . . . . . . . . . . . . . . . . . . . . . . . . 3/4 0-1 .

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 REACTIVITY CONTROL . . . . . . . . . . 3/4 1-1 I Shutdown Margin (SDM) . . . . . . . . . 3/4 1-1 I Reactivity Balance . . . . . . . . . . 3/4 1-2 I DELETED . . . . . . . . . . . . . . . . 3/4 1-3 I Boron Dilution . . . . . . . . . . . . 3/4 1-4 Moderator Temperature Coefficient (MTC) 3/4 1-5 Minimum Temperature for Criticality . . 3/4 1-7 3/4. 1.2 BORATION SYSTEMS . . . . . . . . 3/4 1-8 Flow Paths - Shutdown . . . . . . 3/4 1-8 Flow Paths - Operating . . . . . 3/4 1-9 Charging Pump - Shutdown . . . . 3/4 1-11 Charging Pumps - Operating . . . 3/4 1-13 Boric Acid Pumps - Shutdown 3/4 1-14 Boric Acid Pumps - Operating 3/4 1-15 Borated Water Sources - Shutdown 3/4 1-16 Borated Water Sources - Operating 3/4 1-18 3/4.1.3 MOVABLE CONTROL ASSEMBLIES . . . 3/4 1-20 CEA Group Position . . . . . . . 3/4 1-20 I Position Indicator Channels . . . 3/4 1-24 CEA Drop Time . . . . . . . . . 3/4 1-26 Shutdown CEA Insertion Limit . . 3/4 1-27 Regulating CEA Insertion Limits 3/4 1-28 Control Rod Drive Mechanisms . . 3/4 1-31 MILLSTONE - UNIT 2 IV Amendment No. .B , log, 280 ,

0844 fl, ,r9Y. 280

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION . . . . . . . . . . . . . . . . . . . 3/4 9-1 3/4.9.2 INSTRUMENTATION .................... 3/4 9-2 3/4.9.3 DECAY TIME . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-3 3/4.9.4 CONTAINMENT PENETRATIONS ........ ... ... . . 3/4 9-4 3/4.9.5 DELETED . ................... 3/4 9-5 3/4.9.6 DELETED . ................... 3/4 9-6 3/4.9.7 DELETED.. .................. 3/4 9-7 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION . . . . . . . . 3/4 9-8 High Water Level .................... 3/4 9-8 Low Water Level .................... 3/4 9-8b 3/4.9.9 DELETED.. .................. 3/4 9-9 3/4.9.10 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-10 3/4.9.11 WATER LEVEL - REACTOR VESSEL . . . . . . . . . . . . . . 3/4 9-11 3/4.9.12 STORAGE POOL WATER LEVEL . . . . . . . . . . . . . . . . 3/4 9-12 3/4.9.13 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-13 3/4.9. 14 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-14 3/4.9.15 STORAGE POOL AREA VENTILATION SYSTEM . . . . . . . . . . 3/4 9-16 3/4.9.16 SHIELDED CASK . . . . . . . . . . . . . . . . . . . . . . 3/4 9-19 3/4.9.17 SPENT FUEL POOL BORON CONCENTRATION . . . . . . . . . . . 3/4 9-21 3/4.9.18 SPENT FUEL POOL - STORAGE ....... .... ... . . 3/4 9-22 3/4.9.19 SPENT FUEL POOL - STORAGE PATTERN . . . . . . . . . . . . 3/4 9-26 3/4.9.20 SPENT FUEL POOL - CONSOLIDATION . . . . . . . . . . . . 3/4 9-27 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN . . . . . . . . . . . . . . . . . . . . 3/4 10-1 3/4.10.2 GROUP HEIGHT AND INSERTION LIMITS . . . . . . . . . . 3/4 10-2 3/4.10.3 DELETED . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-3 I MILLSTONE - UNIT 2 IX Amendment No. #i. 0#. My 0845 117 ,IfFIf?, If?,If I , 7%, 280

INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.10.4 DELETED . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-4 I 3/4.10.5 DELETED . . . . . . .. .. . . . . . . . . . . . . . 3/4 10-5 I 3/4.11 DELETED 3/4.11.1 DELETED 3/4.11.2 DELETED 3/4. 11.3 DELETED MILLSTONE - UNIT 2 X Amendment No. ,1X, joy, OF/, gyp, 280 0845

INDEX BASES SECTION PAGE 3/4.9.9 and 3/4.9.10 DELETED . . . . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.11 and 3/4.9.12 WATER LEVEL - REACTOR VESSEL AND STORAGE POOL WATER LEVEL . . . . . . . . . . . . . . . B 3/4 9-2a 3/4.9.13 DELETED . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-3 3/4.9.14 DELETED . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-3 3/4.9.15 STORAGE POOL AREA VENTILATION SYSTEM . . . . . . . . . B 3/4 9-3 3/4.9.16 SHIELDED CASK . . . . . B 3/4 9-3b I 3/4.9.17 SPENT FUEL POOL BORON CONCENTRATION . . . . . . . . . . B 3/4 9-3b I 3/4.9.18 SPENT FUEL POOL - STORAGE . . . . . . . . . . . . . . . B 3/4 9-4 I 3/4.9.19 SPENT FUEL POOL - STORAGE PATTERN . . . . . . . . . . B 3/4 9-4 3/4.9.20 SPENT FUEL POOL - CONSOLIDATION . . . . . . . . . . . . B 3/4 9-4 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN . . . . . . . . . . . . . . . . . . . . B 3/4 10-1 3/4.10.2 GROUP HEIGHT AND INSERTION LIMITS . . . . . . . . . . . B 3/4 10-1 3/4.10.3 DELETED .B 3/4 10-1 I 3/4.10.4 DELETED .B 3/4 10-1 I 3/4.10.5 DELETED .B 3/4 10-1 I 3/4.11 DELETED 3/4.11.1 DELETED . B 3/4 11-1 3/4.11.2 DELETED . B 3/4 11-1 3/4.11.3 DELETED . . . . . . . . . . . . . . . . . . . . . . . B 3/4 11-1 MILLSTONE - UNIT 2 XIV Amendment No. #i, }0, }IF, 117, 0846 x

IFFF 2FF0 I UP,* 7ly 280

DEFINITIONS CORE ALTERATION 1.12 CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

SHUTDOWN MARGIN 1.13 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest reactivity worth which is assumed to be fully withdrawn.

IDENTIFIED LEAKAGE 1.14 IDENTIFIED LEAKAGE shall be:

a. Leakage into closed systems, such as pump seal or valve packing leaks that are captured, and conducted to a sump or collecting tank, or

b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE.

UNIDENTIFIED LEAKAGE 1.15 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.

PRESSURE BOUNDARY LEAKAGE 1.16 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall.

CONTROLLED LEAKAGE 1.17 CONTROLLED LEAKAGE shall be the water flow from the reactor coolant pump seals.

MILLSTONE - UNIT 2 1-3 Amendment No. If, Aft, 280 0847

CORE is within the limit specified in the 4.1.1.1 Verify SHUTDOWN MARGIN 3/4.1 REACTVITY CONTROL SYSTEMS 3/4.1.1 REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - (SDM)

LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be within the limit specified in the CORE OPERATING LIMITS REPORT.

APPLICABILITY: MODES 3"1', 4 and 5.

ACTION:

With the SHUTDOWN MARGIN not within the limit specified in the CORE OPERATING LIMITS REPORT, within 15 minutes, initiate and continue boration at 2 40 gpm of boric acid solution at or greater than the required refueling water storage tank (RWST) concentration (ppm) until the SHUTDOWN MARGIN is restored to within limit.

SURVEILLANCE REQUIREMENT 4.1.1.1 Verify SHUTDOWN MARGIN is within the limit specified in the CORE OPERATING LIMITS REPORT at least once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

(i1 See Special Test Exception 3.10.1 MILLSTONE - UNIT 2 3/4 1-1 Amendment No. Ad, yJ9 7Z, 7*,

0848 Jfl, Iff,280

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MILLSTONE - UNIT 2 3/4 1-2 Amendment No. Ifl, 28O 0848

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 REACTIVITY CONTROL SYSTEMS REACTIVITY BALANCE LIMITING CONDITION FOR OPERATION 3.1.1.2 The core reactivity balance shall be within + 1% Ak/k of predicted values.

APPLICABILITY: MODES 1 and 2.

ACTION:

With core reactivity balance not within limit:

Re-evaluate core design and safety analysis and determine that the reactor core is acceptable for continued operation and establish appropriate operating restrictions and Surveillance Requirements within 7 days or otherwise be in MODE 3 within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENT 4.1.1.2 Verify"' overall core reactivity balance is within + 1% Ak/k of predicted values prior to entering MODE 1 after fuel loading and at least once every 31 Effective Full Power Days1 2K. The provisions of Specification 4.0.4 are not applicable.

(1) The predicted reactivity values may be adjusted (normalized) to correspond to the measured core reactivity prior to exceeding a fuel burnup of 60 Effective Full Power Days after each fuel loading.

(2) Only required after 60 Effective Full Power Days.

3/4 1-3 AMENDMENT NO. Aft, 280 0848

REACTIVITY CONTROL SYSTEMS BORON DILUTION LIMITING CONDITION FOR OPERATION 3.1.1.3 The flow rate of reactor coolant through the core shall be

> 1000 gpm whenever a reduction in Reactor Coolant System boron concentration is being made.

APPLICABILITY: ALL MODES.

ACTION:

With the flow rate of reactor coolant through the core < 1000 gpm, immediately suspend all operations involving a reduction in boron concentration of the Reactor Coolant System.

SURVEILLANCE REQUIREMENTS 4.1.1.3* The reactor coolant flow rate through the core shall be determined to be > 1000 gpm prior to the start of and at least once per hour during a reduction in the Reactor Coolant System boron concentration by either:

a. Verifying at least one reactor coolant pump is in operation, or

b. Verifying that at least one low pressure safety injection pump is in operation and supplying 2 1000 gpm through the core.

When the plant is in MODE 1 or 2, reactor coolant pumps are required to be in operation. Therefore, Surveillance Requirement 4.1.1.3 does not have to be performed in MODES I and 2. I MILSTOE NI 3/4 1-4 Amendment No. Xfg, 779,280

REACTIVITY CONTROL SYSTEMS MINIMUM TEMPERATURE FOR CRITICALITY LIMITING CONDITION FOR OPERATION 3.1.1.5 The Reactor Coolant System temperature (Tavg) shall be > 515OF when the reactor is critical.

APPLICABILITY: MODES 1 and 2#.

ACTION:

With the Reactor Coolant System temperature (Tavg) < 515F, restore Tavg to within its limit within 15 minutes or be in HOT STANDBY within the next 15 minutes.

SURVEILLANCE REQUIREMENTS 4.1.1.5 The Reactor Coolant System temperature (Tavg) shall be determined to be > 515'F.

a. Within 15 minutes prior to making the reactor critical, and

b. At least once per hour when the reactor is critical and the Reactor Coolant System temperature (TIvg) is < 525*F.

With Keff > 1.0.

MILLSTONE - UNIT 2 3/4 1-7 AMENDMENT NO. If, 280 0849

REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES CEA POSITION LIMITING CONDITION FOR OPERATION 3.1.3.1 All CEAs shall be OPERABLE with each CEA of a given group positioned within 10 steps (indicated position) of all other CEAs in its group, and the CEA Motion Inhibit and the CEA Deviation Circuit shall be OPERABLE.

APPLICABILITY: MODES 1"' and 2"'.

ACTION:

INOPERABLE EQUIPMENT REQUIRED ACTION A. One or more CEAs A.1 Reduce THERMAL POWER to < 70% of the trippable and misaligned maximum allowable THERMAL POWER within 1 from all other CEAs in its hour and restore CEA(s) misalignment within group by > 10 steps and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or otherwise be in MODE 3 within the

< 20 steps. next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

OR One CEA trippable and misaligned from all other CEAs in its group by > 20 steps.

B. CEA Motion Inhibit B.1 Verify the indicated position of each inoperable. CEA to be within 10 steps of all other CEAs in its group within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter, and restore CEA Motion Inhibit to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or otherwise be in MODE 3 within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

OR B.2" 2 ' Place and maintain the CEA drive system mode switch in either the "off" or "manual" position, and withdraw all CEAs in group 7 to > 172 steps within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or otherwise be in MODE 3 within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

(1) See Special Test Exception 3.10.2 (2) Performance of Action B.2 is allowed only when not in conflict with either Required Action A.1 or C.1.

MILLSTONE - UNIT 2 3/4 1-20 AMENDMENT NO. fl, 280 0850

REACTIVITY CONTROL SYSTEMS ACTION (Continued):

C. CEA Deviation Circuit C.1 Verify the indicated position of each CEA inoperable. to be within 10 steps of all other CEAs in its group within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter or otherwise be in MODE 3 within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

D. One or more CEAs D.1 Be in MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

untrippable.

OR Two or more CEAs misaligned by > 20 steDs.

SURVEILLANCE REQUIREMENTS 4.1.3.1.1 Verify the indicated position of each CEA to be within 10 steps

.of all other CEAs in its group at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months following any CEA movement larger than 10 steps.

4.1.3. 1.2 Verify CEA freedom of movement (trippability) by moving each individual CEA that is not fully inserted into the reactor core 10-steps in either direction at least once per 92 days.

4.1.3. 1.3 Verify the CEA Deviation Circuit is OPERABLE at least once per 92 days by a functional test of the CEA group Deviation Circuit which verifies that the circuit prevents any CEA from being misali ned from all other CEAs in its group by more than 10 steps {indicated position).

4.1.3. 1.4 Verify the CEA Motion Inhibit is OPERABLE by a functional test which verifies that the circuit maintains the CEA group overlap and sequencing requirements of Specification 3.1.3.6 and that the circuit prevents regulating CEAs from being inserted beyond the Transient Insertion Limits specified in the CORE OPERATING LIMITS REPORT:

a. Prior to each entry into MODE 2 from MODE 3, except that such verification need not be performed more often than once per 31 days, and

b. At least once per 6 months.

MILLSTONE - UNIT 2 3/4 1-21 AMENDMENT NO. 7Z, 280 0850

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MILLSTONE - UNIT 2 3/4 1-22 Amendment No. 7H9, ac 280 0850

REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS LIMITING CONDITION FOR OPERATION 3.1.3.3 All shutdown and regulating CEA reed switch position indicator channels and CEA pulse counting position indicator channels shall be OPERABLE and capable of determining the absolute CEA positions within +

3 steps.

APPLICABILITY: MODES 1 and 2.

ACTION:

a. Deleted.

b. With a maximum of one reed switch position indicator channel per group or one (except as permitted by ACTION item d. below) pulse counting position indicator channel per group inoperable and the CEA(s) with the inoperable position indicator channel partially inserted, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

1. Restore the inoperable position indicator channel to OPERABLE status, or

2. Be in HOT STANDBY, or

3. Reduce THERMAL POWER to < 70% of the maximum allowable THERMAL POWER level; if negative reactivity insertion is required to reduce THERMAL POWER, boration shall be used.

Operation at or below this reduced THERMAL POWER level may continue provided that within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

a) The CEA group(s) with the inoperable position indi-cator is fully withdrawn while maintaining the withdrawal sequence required by Specification 3.1.3.6 and when this CEA group reaches its fully withdrawn position, the "Full Out" limit of the CEA with the inoperable position indicator is actuated and verifies this CEA to be fully withdrawn. Sub-sequent to fully withdrawing this CEA group(s), the THERMAL POWER level may be returned to a level consistent with all other applicable specifications; or MILLSTONE - UNIT 2 3/4 1-24 Amendment No. If, 280 0851

REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS (Continued)

LIMITING CONDITION FOR OPERATION (Continued) b) The CEA group(s) with the inoperable indicator is fully inserted, and subsequently maintained fully inserted, while maintaining the withdrawal sequence and THERMAL POWER level required by Specification 3.1.3.6 and when this CEA group reaches its fully inserted position, the "Full In" limit of the CEA with the inoperable position indicator is actuated and verifies this CEA to be fully inserted.

Subsequent operation shall be within the limits of Specification 3.1.3.6.

4. If the failure of the position indicator channel(s) is during STARTUP, the CEA group(s) with the inoperable position indicator channel must be moved to the "Full Out" position and verified to be fully withdrawn via a "Full But" indicator within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

c. With a maximum of one reed switch position indicator channel per group or one pulse counting position indicator channel per group inoperable and the CEA(s) with the inoperable position indicator channel at either its fully inserted position or fully withdrawn position, operation may continue provided:

1. The position of this CEA is verified immediately and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter by its "Full In" or "Full Out" limit (as applicable).

2. The fully inserted CEA group(s) containing the inoperable position channel is subsequently maintained fully inserted, and

3. Subsequent operation is within the limits of Specification 3.1.3.6.

d. With one or more pulse counting position indicator channels inoperable, operation in MODES 1 and 2 may continue for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months provided all of the reed switch position indicator channels are OPERABLE.

SURVEILLANCE REQUIREMENTS 4.1.3.3 Each position indicator channel shall be determined to be OPERABLE by verifying the pulse counting position indicator channels and the reed switch position indicator channels agree within 6 steps at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

MILLSTONE - UNIT 2 3/4 1-25 Amendment No. IfJ, 280 085 1

REACTIVITY CONTROL SYSTEMS CEA DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual CEA drop time, from a fully withdrawn position, shall be < 2.75 seconds from when electrical power is interrupted to the CEA drive mechanism until the CEA reaches its 90 percent insertion position with:

a. T.vg 2 515°F, and

b. All reactor coolant pumps operating.

APPLICABILITY: MODES 1 and 2.

ACTION:

With the drop time of any CEA determined to exceed the above limit, restore the CEA drop time to within the above limit prior to proceeding to MODE 1 or 2. I SURVEILLANCE REQUIREMENTS 4.1.3.4 The CEA drop time shall be demonstrated through measurement with Tavp > 515*F, and all reactor coolant pumps operating prior to reactor criticality:

a. For all CEAs following each removal of the reactor vessel head,

b. For specifically affected individual CEAs following any main-tenance on or modification to the CEA drive system which could affect the drop time of those specific CEAs, and

c. At least once per 18 months.

MILLSTONE - UNIT 2 3/4 1-26 Amendment No. I?, PI, pp, gXP, 280 0851

REACTIVITY CONTROL SYSTEMS SHUTDOWN CEA INSERTION LIMIT LIMITING CONDITION FOR OPERATION 3.1.3.5 All shutdown CEAs shall be withdrawn to > 176 steps.

APPLICABILITY: MODE 11'"

MODE 2z"1 23with any regulating CEA not fully inserted.

ACTION:

INOPERABLE EQUIPMENT REQUIRED ACTION A. One or more shutdown CEAs not A.1 Restore shutdown CEA(s) to within limit. within limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or otherwise be in MODE 3 within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.3.5 Verify each shutdown CEA is withdrawan > 176 steps at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

(1) This LCO is not applicable while performing Specification 4.1.3.1.2.

(21 See Special Test Exceptions 3.10.1 and 3.10.2.

MILLSTONE - UNIT 2 3/4 1-27 Amendment No. 280 0851

REACTIVITY CONTROL SYSTEMS REGULATING CEA INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6 The power dependent insertion limit (PDIL) alarm circuit shall be OPERABLE, and the regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits specified in the CORE OPERATING LIMITS REPORT.

APPLICABILITY'": MODES 1(2) and 2(2z)3)

ACTION:

INOPERABLE EQUIPMENT REQUIRED ACTION A. Regulating CEA A.1 Restore regulating CEA groups to within groups inserted limits specified in the CORE OPERATING LIMITS beyond the Transient REPORT within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or otherwise be in MODE 3 Insertion Limits within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

provided in the CORE OPERATING LIMITS OR REPORT.

A.2 Reduce THERMAL POWER to less than or equal to the fraction of RATED THERMAL POWER allowed by the CEA group position and insertion limits specified in the CORE OPERATING LIMITS REPORT within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or otherwise be in MODE 3 within l_____________________ the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

(1)

This LCO is not applicable while performing Specification 4.1.3.1.2.

12)

See Special Test Exceptions 3.10.1 and 3.10.2.

13) With Koff > 1.0 MILLSTONE - UNIT.2 0851 3/4 1-28 Amendment gy, JW, 280

REACTIVITY CONTROL SYSTEMS REGULATING CEA INSERTION LIMITS (Continued)

B. Regulating CEA groups B.1 Verify Short Term Steady State inserted between the Long Insertion Limits as specified in the CORE Term Steady State OPERATING LIMITS REPORT are not exceeded Insertion limit and the within 15 minutes or otherwise be in MODE Transient Insertion Limit 3 within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

specified in the CORE OPERATING LIMITS REPORT OR for intervals > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval. B.2 Restrict increases in THERMAL POWER to < 5% RATED THERMAL POWER per hour within 15 minutes or otherwise be in MODE 1*

3 within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

C. Regulating CEA groups C.1 Restore regulating CEA groups to inserted between the Long within the Long Term Steady State Term Steady State Insertion Limit specified in the CORE Insertion Limit and the OPERATING LIMITS REPORT within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or Transient Insertion Limit otherwise be in MODE 3 within the next 6 specified in the CORE hours.

OPERATING LIMITS REPORT for intervals > 5 effective full power days (EFPD) per 30 EFPD or interval > 14 EFPD per 365 EFPD.

D. PDIL alarm circuit D.1 Perform Specification 4.1.3.6.1 inoperable. within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter or otherwise be in MODE 3 within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.3.6.1 Verify each regulating CEA group position is within the Transient Insertion Limits specified in the CORE OPERATING LIMITS REPORT at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The provisions of Specification 4.0.4 are not applicable for entering into MODE 2 from MODE 3.

4.1.3.6.2 Verify the accumulated times during which the regulating CEA groups are inserted beyond the Steady State Insertion Limits but within the Transient Insertion Limits specified in the CORE OPERATING LIMITS REPORT at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.1.3.6.3 Verify PDIL alarm circuit is OPERABLE at least once per 31 days.

MILLSTONE - UNIT 2 3/4 1-29 Amendment AIf, jF}, thy. 280 0851

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENT (Continued) 4.2.1.2 Excore Detector Monitoring Svstem"1 ) - The excore detector monitoring system may be used for monitoring the core power distribution by:

a. Verifying at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months that the CEAs are withdrawn to I and maintained at or beyond the Long Term Steady State Insertion Limits of Specification 3.1.3.6.

b. Verifying at least once per 31 days that the AXIAL SHAPE INDEX alarm setpoints are adjusted to within the allowable limits specified in the CORE OPERATING LIMITS REPORT.

4.2.1.3 3' Incore Detector Monitoring Svstem 2 1 ,1 - The incore detector I monitoring system may be used for monitoring the core power distribution by verifying that the incore detector Local Power Density alarms:

a. Are adjusted to satisfy the requirements of the core power distribution map which shall be updated at least once per 31 days.

b. Have their alarm setpoint adjusted to less than or equal to the limits specified in the CORE OPERATING LIMITS REPORT. I 11 Only required to be met when the Excore Detector Monitoring System is being used to determine Linear Heat Rate.

(21 Only required to be met when the Incore Detector Monitoring System is being used to determine Linear Heat Rate.

'31 Not required to be performed below 20% RATED THERMAL POWER.

MILLSTONE - UNIT 2 3/4 2-2 Amendment No. 77, Ah, 97, 0852 77, ares cog' 280

POWER DISTRIBUTION LIMITS TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR - FT, LIMITING CONDITION FOR OPERATION 3.2.3 The calculated value of FT. shall be within the 100% power limit specified in the CORE OPERATING LIMITS REPORT. The FTr value shall include the effect of AZIMUTHAL POWER TILT.

APPLICABILITY: MODE 1 with THERMAL POWER >20% RTP*.

ACTION:

With FTr exceeding the 100% power limit within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either:

a. Reduce THERMAL POWER to bring the combination of THERMAL POWER and FTr to within the power dependent limit specified in the CORE OPERATING LIMITS REPORT and withdraw the CEAs to or beyond the Long Term Steady I State Insertion Limits of Specification 3.1.3.6; or

b. Be in at least HOT STANDBY.

SURVEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 FTr shall be determined to be within the 100% power limit at the following intervals:

a. Prior to operation above 70 percent of RATED THERMAL POWER after each fuel loading,

b. At least once per 31 days of accumulated operation in Mode 1, and

c. Within four hours if the AZIMUTHAL POWER TILT (Tq) is > 0.020.

4.2.3.3 FTr shall be determined by using the incore detectors to obtain a power distribution map with all CEAs at or above the Long Term Steady State I Insertion Limit for the existing Reactor Coolant Pump Combination.

See Special Test Exception 3.10.2 MILLSTONE - UNIT 2 3/4 2-9 Amendment No. IF, M, 7Y, P, PI, 0853Z. Aid. OF. tHY. Iff, 779, 280

POWER DISTRIBUTION LIMITS AZIMUTHAL POWER TILT - T q LIMITING CONDITION FOR OPERATION 3.2.4 The AZIMUTHAL POWER TILT (Tq) shall be < 0.02. APPLICABILITY: MODE 1 with THERMAL POWER > 50% of RATED THERMAL POWER"'. ACTION:

a. With the indicated Tq > 0.02 but -<0.10, either restore Tq to < 0.02 within 2 hours or verify the TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR (FTr) is within the limit of Specification 3.2.3 within 2 hours and once per 8 hours thereafter. Or otherwise, reduce THERMAL POWER to < 50% of RATED THERMAL POWER within the next 4 hours.

b. With the indicated Tq > 0.10, perform the following actions: 2 )

1. Verify the TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR (FTr) is within the limit of Specification 3.2.3 within 2 hours; and

2. Reduce THERMAL POWER to < 50% of RATED THERMAL POWER within 2 hours; and

3. Restore Tq < 0.02 prior to increasing THERMAL POWER. Correct the cause of the out of limit condition prior to increasing THERMAL POWER. Subsequent power operation above 50% of RATED THERMAL POWER may proceed provided that the measured Tq is verified < 0.02 at least once per hour for 12 hours, or until verified at 95% of RATED THERMAL POWER.

SURVEILLANCE REQUIREMENTS 4.2.4.1 Verify Tq is within limit at least once every 12 hours. The provisions of Specification 4.0.4 are not applicable for entering into MODE I with THERMAL POWER > 50% of RATED THERMAL POWER from MODE 1. i1) See Special Test Exception 3.10.2. 21 All subsequent Required Actions must be completed if power reduction commences prior to restoring Tq < 0.10. MILLSTONE - UNIT 2 3/4 2-10 Amendment No. Ah, At, yp, 0853 Aids AdF 280

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MILLSTONE - UNIT 2 3/4 2-11 Amendment No. 280 0853

TABLE 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION cf MINIMUM b-4 2O TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

1. Manual Reactor Trip 2 1 1, 2 and

1

2. Power Level - High 4 2(f) 1, 2, 3(d) 2

3. Reactor Coolant Flow - Low 4 2(a) 1, 2 2 I

4. Pressurizer Pressure - High 4 2 1, 2 2

5. Containment Pressure - High 4 2 1, 2 2

6. Steam Generator Pressure - Low 4 2(b) 1, 2 2

7. Steam Generator Water Level - Low 4 2 1, 2 2

8. Local Power Density - High 4 2(c) 1 2 r9 2

9. Thermal Margin/Low Pressure 4 2(a) 1,2 2 I M

10. Loss of Turbine - Hyraulic Fluid Pressure - Low 4 2(c) 1 2 It"3 0

TABLE 3.3-1 (Continued) REACTOR PROTECTIVE INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

11. Wide Range Logarithmic Neutron 4 0 2 3,4,5 4 Flux Monitor - Shutdown

12. Underspeed - Reactor Coolant Pumps 4 2(a) 3 1,2 2 I

TABLE 3.3-1 (Continued) TABLE NOTATION

With the protective system trip breakers in the closed position and the CEA drive system capable of CEA withdrawal.

(a) Trip may be bypassed below 5% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is > 5% of RATED THERMAL POWER. (b) Trip may be manually bypassed when steam generator pressure is < 800 psia and all CEAs are fully inserted; bypass shall be automatically removed when steam generator pressure is > 800 psia. (c) Trip may be bypassed below 15% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is > 15% of RATED THERMAL POWER. (d) Trip does not need to be operable if all the control rod drive mechanisms are de-energized or if the RCS boron concentration is greater than or equal to the refueling concentration of Specification 3.9.1. (e) DELETED (f) AT Power input to trip may be bypassed below 5% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is > 5% of RATED THERMAL POWER. ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours or be in HOT STANDBY within the next 4 hours and/or open the protective system trip breakers. ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may continue provided the following conditions are satisfied:

a. The inoperable channel is placed in either the bypassed or tripped condition within 1 hour. The inoperable channel shall either be restored to OPERABLE status, or placed in the tripped condition, within 48 hours.

b. Within 1 hour, all functional units receiving an input from the inoperable channel are also declared inoperable, and the appropriate actions are taken for the affected functional units.

c. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be removed from service for up to 48 hours, provided one of the inoperable channels is placed in the tripped condition.

MILLSTONE - UNIT 2 3/4 3-4 Amendment No. i, IF 77, dfd, Add, 280 0854 li I M

TABLE 3.3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION o = I-co MINIMUM

  -I TOTAL NO.        CHANNELS    CHANNELS     APPLICABLE FUNCTIONAL UNIT                        OF CHANNELS      TO TRIP     OPERABLE         MODES   ACTION 04

1. SAFETY INJECTION (SIAS) (d)

a. Manual (Trip Buttons) 2 1 2 1, 2, 3, 4 1

b. Containment Pressure -

High 4 2 3 1, 2, 3 2

c. Pressurizer Pressure -

Low 4 2 3 1, 2, 3(a) 21

2. CONTAINMENT SPRAY (CSAS)

a. Manual (Trip Buttons) 2 1 2 1, 2, 3, 4 1

b. Containment Pressure--

High - High 4 2(b) 3 1, 2, 3 2 W 3. CONTAINMENT ISOLATION (CIAS)

"3

a. Manual CIAS (Trip Buttons) 2 1 2 1, 2, 3, 4 1 I-M b. Manual SIAS (Trip Buttons) 2 1 2 1, 2, 3, 4 1

c. Containment Pressure -

High 4 2 3 1, 2, 3 2

0. d. Pressurizer Pressure -

ED Low 4 2 3 1, 2, 3(a) 21 0 Ta

TABLE 3.3-3 (Continued) TABLE NOTATION (a) Trip function may be bypassed when pressurizer pressure is < 1850 psia; bypass shall be automatically removed when pressurizer pressure is > 1850 psia. (b) An SIAS signal is first necessary to enable CSAS logic. (c) Trip function may be bypassed when steam generator pressure is < 700 psia; bypass shall be automatically removed when steam generator pressure is > 700 psia. (d) In MODE 4 the HPSI pumps are not required to start automatically on a SIAS. (e) DELETED I ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours or be in COLD SHUTDOWN within the next 36 hours. ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may continue provided the following conditions are satisfied:

a. The inoperable channel is placed in either the bypassed or tripped condition within 1 hour. The inoperable channel shall either be restored to OPERABLE status, or placed in the tripped condition, within 48 hours.

b. Within 1 hour, all functional units receiving an input from the inoperable channel are also declared inoperable, and the appropriate actions are taken for the affected functional units.

c. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be removed from service for up to 48 hours, provided one of the inoperable channels is placed in the tripped condition.

MILLSTONE - UNIT 2 3/4 3-16 t77, Amendment No. Af77,, , 7Z, 0856 A, 7177 280

REACTOR COOLANT SYSTEM 3/4.4.9 PRESSURE/TEMPERATURE LIMITS REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION 3.4.9.1 Reactor Coolant System (except the pressurizer) temperature, pressure, and heatup and cooldown rates shall be limited in accordance with the limits specified in Table 3.4-2 and shown on Figures 3.4-2a and 3.4-2b. APPLICABILITY: At all times. I ACTION:

a. With any of the above limits exceeded in MODES 1, 2, 3, or 4, perform the following:

1. Restore the temperature and/or pressure to within limit within 30 minutes.

AND

2. Perform an engineering evaluation to determine the effects of the out of limit condition on the structural integrity of the Reactor Coolant System and determine that the Reactor Coolant System remains acceptable for continued operation within 72 hours. Otherwise, be in at least MODE 3 within the next 6 hours and in MODE 5 with RCS pressure less than 300 psia within the following 30 hours.

b. With any of the above limits exceeded in other than MODES 1, 2, 3, or 4, perform the following:

1. Immediately initiate action to restore the temperature and/or pressure to within limit.

AND

2. Perform an engineering evaluation to determine the effects of the out of limit condition on the structural integrity of the Reactor Coolant System and determine that the Reactor Coolant System is acceptable for continued operation prior to entering MODE 4.

I MILLSTONE - UNIT 2 3/4 4-17 Amendment No. fg, 7f, Aid, 0857 Aid, tIf, 280

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATIONS LIMITING CONDITION FOR OPERATION 3.9.1 The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained sufficient to ensure that the more restrictive of following reactivity conditions is met:

a. Either a Keff of 0.95 or less, or

b. A boron concentration of greater than or equal to 1720 ppm.

APPLICABILITY: MODE 6. NOTE Only applicable to the refueling canal when connected to the Reactor Coolant System ACTION: With the requirements of the above specification not satisfied, within 15 minutes suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 40 gpm of boric acid solution at or greater than the required refueling water storage tank concentration (ppm) until Keff is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to 1720 ppm, whichever is the more restrictive. SURVEILLANCE REQUIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:

a. Removing or unbolting the reactor vessel head, and

b. Withdrawal of any CEA in excess of 3 feet from its fully inserted position within the reactor pressure vessel.

4.9.1.2 The boron concentration of all filled portions of the reactor coolant system and the refueling canal shall be determined by chemical analysis at least once per 72 hours. 4.9.1.3 Deleted MILLSTONE - UNIT 2 3/4 9-1 Amendment No. ty, g7ai 280 0858

3/4.10 SPECIAL TEST EXCEPTIONS I SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.10.1 The requirement of Specifications 3.1.1.1, 3.1.3.5 and 3.1.3.6 may be suspended for measurement of CEA worth and shutdown margin provided reactivity equivalent to at least the highest estimated CEA worth (of those CEAs actually withdrawn) is available for trip insertion from OPERABLE CEA(s). APPLICABILITY: MODES 2 and 3V' during PHYSICS TESTS. ACTION:

a. With any CEA not fully inserted and with less than the above reactivity equivalent available for trip insertion, within 15 minutes initiate and continue boration at > 40 gpm of boric acid solution at or greater than the required refueling water storage tank (RWST) concentration (ppm) until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

b. With all CEAs inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at > 40 gpm of boric acid solution at or greater than the required refueling water storage tank (RWST) concentration (ppm) until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

SURVEILLANCE REQUIREMENTS 4.10.1.1 The position of each CEA required either partially or fully withdrawn shall be determined at least once per 2 hours. 4.10.1.2 Each CEA not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50% withdrawn position once within 7 days prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.112). '" Operation in MODE 3 shall be limited to 6 consecutive hours.

12) Not required to be performed during initial power escalation following a refueling outage if SR 4.1.3.4 has been met.

MILLSTONE - UNIT 2 3/4 10-1 Amendment No. fl, F7, 77, Add, 280 0859

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MILLSTONE - UNIT 2 3/4 10-3 Amendment No. II?, 0860 280

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MILLSTONE - UNIT 2 3/4 10-4 Amendment No. 280 0860

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ONI MILSTOE 3/4 10-5 Amendment No. I, 20, 2PQ

DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 217 fuel assemblies with each fuel assembly containing 176 rods. Reload fuel shall be similar in physical design to the initial core loading and shall have a minimum nominal average enrichment of 4.85 weight percent of U-235. A fuel rod shall have a maximum enrichment of 5.0 weight percent of U-235. CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 73 control element assemblies. The I control element assemblies shall be designed and maintained in accordance with the design provisions contained in Section 3.0 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements. 5.4 DELETED MILLSTONE - UNIT 2 5-4 Amendment No. Ad, Jpi, Aft, ZiP, 0861 Zig 770 t77f 280

ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT (Con't) Administrator, Region I, and one copy to the NRC Resident Inspector, no later than the 15th of each month following the calendar month covered by the report. CORE OPERATING LIMITS REPORT 6.9.1.8 a. Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle. 3/4.1.1.1 SHUTDOWN MARGIN (SDM) 3/4.1.1.4 Moderator Temperature Coefficient 3/4.1.3.6 Regulating CEA Insertion Limits 3/4.2.1 Linear Heat Rate 3/4.2.3 Total Integrated Radial Peaking Factor - FT 3/4.2.6 DNB Margin

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1) EMF-96-029(P)(A) Volumes 1 and 2, "Reactor Analysis System for PWRs Volume 1 - Methodology Description, Volume 2 -

Benchmarking Results," Siemens Power Corporation.

2) ANF-84-73 Appendix B (P)(A), "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events," Advanced Nuclear Fuels.

3) XN-NF-82-21(P)(A), "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations,"

Exxon Nuclear Company.

4) EMF-84-093(P)(A), "Streamline Break Methodology for PWRs,"

Siemens Power Corporation.

5) XN-75-32(P)(A) Supplements 1 through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company.

6) EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model S-RELAP5 Based," Framatome ANP.

7) EMF-2087(P)(A), "SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation.

MILLSTONE - UNIT 2 6-18a Amendment No. If, PI, 7/%, 777, 0900 11f, lip, lip, osoA Z}X Z!if, 2,8 I~sfig thy. ?PO, 280

3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1.1 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition. SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS TV,. The most restrictive condition occurs at EOL, with TaVg at no load operating temperature, and is associated with a postulated steam line break accident and resulting uncontrolled RCS cooldown. In the analysis of this accident, the minimum SHUTDOWN MARGIN specified in the CORE OPERATING LIMITS REPORT is initially required to control the reactivity transient. Accordingly, the SHUTDOWN MARGIN required by Specification 3.1.1.1 is based upon this limiting condition and is consistent with FSAR accident analysis assumptions. For earlier periods during the fuel cycle, this value is conservative. The SHUTDOWN MARGIN is verified by' performing a reactivity balance calculation, considering the listed reactivity effects:

a. RCS boron concentration;

b. CEA positions;

c. RCS average temperature;

d. Fuel burnup based on gross thermal energy generation;

e. Xenon concentration;

f. Samarium concentration; and

g. Isothermal temperature coefficient (ITC).

Using the ITC accounts for Doppler reactivity in this calculation because the reactor is subcritical and the fuel temperature will be changing at the same rate as the RCS temperature. 3/4.1.1.2 REACTIVITY BALANCE Reactivity balance is used as a measure of the predicted versus measured core reactivity during power operation. The periodic confirmation of core reactivity is necessary to ensure that Design Basis Accident (DBA) and transient safety analyses remain valid. A large reactivity difference could be the result of unanticipated changes in fuel, control element assembly (CEA) worth, or operation at conditions not consistent with those assumed in the predictions of core reactivity, and could potentially result in a loss of SHUTDOWN MARGIN (SDM) or violation of acceptable fuel design limits. Comparing predicted versus measured core reactivity validates the nuclear methods used in the safety analysis and supports the SDM demonstrations (LCO 3.1.1.1, "SHUTDOWN MARGIN (SDM)") in ensuring the reactor can be brought safely to cold, subcritical conditions. The normalization of predicted RCS boron concentration to the measured value is typically performed after reaching RATED THERMAL POWER following startup from a refueling outage, with the CEAs in their normal positions for power operation. The normalization is performed at BOC conditions, so that core B 3/4 1-1 Amendment No. Jfl, 7Ai, 7F9, 2SO 0862

3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 REACTIVITY CONTROL SYSTEMS (Continued) 3/4.1.1.2 REACTIVITY BALANCE (Continued) reactivity relative to predicted values can be continually monitored and evaluated as core conditions change during the cycle. When measured core reactivity is within +1% Ak/k of the predicted value at steady state thermal conditions, the core is considered to be operating within acceptable design limits. The limits on core reactivity must be maintained during MODES 1 and 2 because a reactivity balance must exist when the reactor is critical or producing THERMAL POWER. This Specification does not apply in MODES 3, 4 and 5 because the reactor is shut down and the reactivity balance is not changing. In MODE 6, fuel loading results in a continually changing core reactivity. Boron concentration requirements (LCO 3.9.1, "Boron Concentration") ensure that fuel movements are performed within the bounds of the safety analysis. 3/4.1.1.3 BORON DILUTION A minimum flow rate of at least 1000 GPM provides adequate mixing, prevents stratification and ensures that reactivity changes will be gradual during reductions in Reactor Coolant System boron concentration. The 1000 GPM limit is the minimum required shutdown cooling flow to satisfy the boron dilution accident analysis. This 1000 GPM flow is an analytical limit. Plant operating procedures maintain the minimum shutdown cooling flow at a higher value to accommodate flow measurement uncertainties. While the plant is operating in reduced inventory operations, plant operating procedures also specify an upper flow limit to prevent vortexing in the shutdown cooling system. A flow rate of at least 1000 GPM will circulate the full Reactor Coolant System volume in approximately 90 minutes. With the RCS in mid-loop operation, the Reactor Coolant System volume will circulate in approximately 25 minutes. The reactivity change rate associated with reductions in Reactor Coolant System boron concentration will be within the capability for operator recognition and control. 3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT (MTC) The limitations on MTC are provided to ensure that the assumptions used in the accident and transient analyses remain valid through each fuel cycle. The surveillance requirements for measurement of the MTC during each fuel cycle are adequate to confirm the MTC value since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup. The confirmation that the measured MTC value is within its limit provides assurance that the coefficient will be maintained within acceptable values throughout each fuel cycle. MILLSTONE - UNIT 2 B 3/4 I-la Amendment No. Add, IfF, JAd, 280 0862

BASES 3/4.1.2 BORATION SYSTEMS (Continued) The provision in Specification 3.1.2.4 that Specifications 3.0.4 and 4.0.4 are not applicable for entry into MODE 4 is provided to allow for closing the motor circuit breaker and subsequent testing of the inoperable charging pump. Specification 3.4.9.3, which is applicable to MODES 5 and 6, requires that one charging pump be capable of injecting into the RCS at or below 1900F. Specification 3.1.2.4 requires that at least two charging pumps be OPERABLE in MODES 1, 2, 3, and 4. The exception from Specification 3.0.4 and 4.0.4 will allow Millstone Unit No. 2 to enter into MODE 4 and test the inoperable charging pump and declare it OPERABLE. Surveillance Requirement (SR) 4.1.2.2.a requires all testable power operated valves in each required flow path to be exercised through one complete cycle at least once per 7 days. This surveillance requirement does not apply to 2-CS-13.1B. This motor operated valve is in the RWST supply to the charging pumps and the RWST supply to the Facility 2 emergency core cooling pumps (HPSI, LPSI, and CS). It is key-locked in the open position during normal plant operation. This valve is not in the boration flow path when it is in the normal locked open position, and it is a non-testable valve in Modes 1 through 4 for boration flow path verification due to the increase in plant risk with no offsetting improvement in plant safety. Therefore, it is not necessary to stroke this valve at least once per 7 days for the boration flow path verification required by SR 4.1.2.2.a. However, for additional assurance, 2-CS-13.1B should be verified locked open when performing SR 4.1.2.2.a. 3/4.1.3 MOVEABLE CONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) the potential effects of a CEA ejection accident are limited to acceptable levels. The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original criteria are met. MILLSTONE - UNIT 2 B 3/4 1-3a Amendment No. #J, JJd, Ai, A 280 0863 t

BASES 3/4.1.3 MOVEABLE CONTROL ASSEMBLIES (Continued) A CEA may become misaligned, yet remain trippable. In this condition, the CEA can still perform its required function of adding negative reactivity should a reactor trip be necessary. If one or more CEAs (regulating or shutdown) are misaligned by > 10 steps and < 20 steps but trippable, or one CEA is misaligned by > 20 steps but trippable, continued operation in MODES 1 and 2 may continue, provided, within 1 hour, the power is reduced to < 70% RATED THERMAL POWER, and within 2 hours CEA alignment is restored. If negative reactivity insertion is required to reduce THERMAL POWER, boration shall be used. Regulating CEA alignment can be restored by either aligning the misaligned CEA(s) to within 10 steps of all other CEAs in its group or aligning the misaligned CEA's group to within 10 steps of the misaligned CEA. A Regulating CEA is considered fully inserted when either the Dropped Rod indication or lower Electrical Limit indication lights on the core mimic display are illuminated. A Regulating CEA is considered to be fully withdrawn when withdrawn > 176 steps. Shutdown CEA alignment can only be restored by aligning the misaligned CEA(s) to within 10 steps of its group. Xenon redistribution in the core starts to occur as soon as a CEA becomes misaligned. Reducing THERMAL POWER ensures acceptable power distributions are maintained. For small misalignments (< 20 steps) of the CEAs, there is:

a. A small effect on the time dependent long term power distributions relative to those used in generating LCOs and limiting safety system settings (LSSS) setpoints;

b. A negligible effect on the available SHUTDOWN MARGIN; and

c. A small effect on the ejected CEA worth used in the accident analysis.

With a large CEA misalignment (> 20 steps), however, this misalignment would cause distortion of the core power distribution. This distortion may, in turn, have a significant effect on the time dependent, long term power distributions relative to those used in generating LCOs and LSSS setpoints. The effect on the available SHUTDOWN MARGIN and the ejected CEA worth used in the accident analysis remain small. Therefore, this condition is limited to a single CEA misalignment, while still allowing 2 hours for recovery. In both cases, a 2 hour time period is sufficient to:

a. Identify cause of a misaligned CEA;

b. Take appropriate corrective action to realign the CEAs; and

c. Minimize the effects of xenon redistribution.

If a CEA is untrippable, it is not available for reactivity insertion during a reactor trip. With an untrippable CEA, meeting the insertion limits of LCO 3.1.3.5 and LCO 3.1.3.6 does not ensure that adequate SHUTDOWN MARGIN exists. With one or more CEAs untrippable the plant is transitioned to MODE 3 within 6 hours. MILLSTONE - UNIT 2 B 3/4 1-4 Amendment No. Ad, Aid, M/i, 280 0863

BASES 3/4.1.3 MOVEABLE CONTROL ASSEMBLIES (Continue'd) The CEA motion inhibit permits CEA motion within the requirements of LCO 3.1.3.6, "Regulating Control Element Assembly (CEA) Insertion Limits," and the CEA deviation circuit prevents regulating CEAs from being misaligned from other CEAs in the group. With the CEA motion inhibit inoperable, a time of 6 hours is allowed for restoring the CEA motion inhibit to OPERABLE status, or placing and maintaining the CEA drive switch in either the "off" or "manual" position, fully withdrawing all CEAs in group 7 to < 5% insertion. Placing the CEA drive switch in the "off" or "manual" position ensures the CEAs will not move in response to Reactor Regulating System automatic motion commands. Withdrawal of the CEAs to the positions required in the Required Action B.2 ensures that core perturbations in local burnup, perking factors, and SHUTDOWN MARGIN will not be more adverse than the Conditions assumed in the safety analyses and LCO setpoint determination. Required Action B.2 is modified by a Note indicating that performing this Required Action is not required when in conflict with Required Actions A.1 or C.1. Continued operation is not allowed in the case of more than one CEA misaligned from any other CEA in its group by > 20 steps, or one or more CEAs untrippable. This is because these cases are indicative of a loss of SHUTDOWN MARGIN and power distribution changes, and a loss of safety function, respectively. Operability of the CEA position indicators (Specification 3.1.3.3) is required to determine CEA positions and thereby ensure compliance with the CEA alignment and insertion limits and ensures proper operation of the CEA Motion Inhibit and CEA deviation block circuit. The CEA "Full In" and "Full Out" limit Position Indicator channels provide an additional independent means for determining the CEA positions when the CEAs are at either their fully inserted or fully withdrawn positions. Therefore, the ACTION statements applicable to inoperable CEA position indicators permit continued operations when the positions of CEAs with inoperable position indicators can be verified by the "Full In"or "Full Out" limit Position Indicator channels. CEA positions and OPERABILITY of the CEA position indicators are required to be verified on a nominal basis of once per 12 hours with more frequent verifications required if an automatic monitoring channel is inoperable. These verification frequencies are adequate for assuring that the applicable LCO's are satisfied. The maximum CEA drop time permitted by Specification 3.1.3.4 is the assumed CEA drop time used in the accident analyses. Measurement with T8, > 515OF and With all reactor coolant pumps operating ensures that the measures drop times will be representative of insertion times experienced during a reactor trip at operating conditions. MILLSTONE - UNIT 2 0863 B 3/4 1-4a Amendment No. Jfl, gig, 280

REACTIVITY CONTROL SYSTEMS BASES 3/4.1.3 MOVABLE CONTROL ASSEMBLIES (Continued) The LSSS setpoints and the power distribution LCOs were generated based upon a core burnup which would be achieved with the core operating in an essentially unrodded configuration. Therefore, the CEA insertion limit specifications require that during MODES 1 and 2, the CEAs be nearly fully withdrawn. The amount of CEA insertion permitted by the Long Term Steady State Insertion Limits of Specification 3.1.3.6 will not have a significant effect upon the unrodded burnup assumption but will still provide sufficient reactivity control. The Transient Insertion Limits of Specification 3.1.3.6 are provided to ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) the potential effects of a CEA ejection accident are limited to acceptable levels; however, long term operation at these insertion limits could have adverse effects on core power distribution during subsequent operation in an unrodded configura-tion. The PDIL alarm, CEA Motion Inhibit and CEA deviation circuit are provided by the CEAPDS computer. The control rod drive mechanism requirement of specification 3.1.3.7 is provided to assure that the consequences of an uncontrolled CEA withdrawal from subcritical transient will stay within acceptable levels. This specification assures that reactor coolant system conditions exist which are consistent with the plant safety analysis prior to energizing the control rod drive mechanisms. The accident is precluded when conditions exist which are inconsistent with the safety analysis since deenergized drive mechanisms cannot withdraw a CEA. The drive mechanisms may be energized with the boron concentration greater than or equal to the refueling concentration since, under these conditions, adequate SHUTDOWN MARGIN is maintained, even if all CEAs are fully withdrawn from the core. MILLSTONE - UNIT 2 B 3/4 1-5 Amendment No. I?, Alp, god, 280 0864

3/4.2 POWER DISTRIBUTION LIMITS BASES 3/4.2.1 LINEAR HEAT RATE The limitation on linear heat rate ensures that in the event of a LOCA, the peak temperature of the fuel cladding will not exceed 22000F. Either of the two core power distribution monitoring systems, the Excore Detector Monitoring System and the Incore Detector Monitoring System, provide adequate monitoring of the core power distribution and are capable of verifying that the linear heat rate does not exceed its limits. The Excore Detector Monitoring System performs this function by continuously monitoring the AXIAL SHAPE INDEX with two OPERABLE excore neutron flux detectors and verifying that the AXIAL SHAPE INDEX is maintained within the allowable limits specified in the Core Operating Limits Report using the Power Ratio Recorder. The power dependent limits of the Power Ratio Recorder are less than or equal to the limits specified in the Core Operating Limits Report. In conjunction with the use of the excore monitoring system and in establishing the AXIAL SHAPE INDEX limits, the following assumptions are made: 1) the CEA insertion limits of Specifications 3.1.3.5 and 3.1.3.6 are satisfied, 2) the AZIMUTHAL POWER TILT restrictions of Specification 3.2.4 are satisfied, and 3) the TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR does not exceed the limits of Specification 3.2.3. The Incore Detector Monitoring System continuously provides a direct measure of the peaking factors and the alarms which have been established for the individual incore detector segments ensure that the peak linear heat rates will be maintained within the allowable limits specified in the Core Operating Limits Report. The setpoints for these alarms include allowances, set in the conservative direction. The Incore Detector Monitoring System is not used to monitor linear heat rate below 20% of RATED THERMAL POWER. The accuracy of the neutron flux information from the incore detectors is not reliable at THERMAL POWER < 20% RATED THERMAL POWER. 3/4.2.3 and 3/4.2.4 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTORS FTr AND AZIMUTHAL POWER TILT - Tq The limitations on FT, and Tq are provided to 1) ensure that the assump-tions used in the analysis for establishing the Linear Heat Rate and Local power Density - High LCOs and LSSS setpoints remain valid during operation at the various allowable CEA group insertion limits, and, 2) ensure that the assumptions used in the analysis establishing the DNB Margin LCO, and Thermal Margin/Low Pressure LSSS setpoints remain valid during operation at the various allowable CEA group insertion limits. If FT, or T exceed their basic limitations, operation may continue under the additional restrictions imposed MILLSTONE - UNIT 2 B 3/4 2-1 Amendment No. A, h, FE, 0865 yip, Me Uy, MI, lip 280

POWER DISTRIBUTION LIMITS BASES by the ACTION statements since these additional restrictions provide adequate provisions to assure that the assumptions used in establishing the Linear Heat Rate, Thermal Margin/Low Pressure and Local Power Density - High LCOs and LSSS setpoints remain valid. An AZIMUTHAL POWER TILT > 0.10 is not expected and if it should occur, subsequent operation would be restricted to only those operations required to identify the cause of this unexpected tilt. Core power distribution is a concern any time the reactor is critical. The Total Integrated Radial Peaking Factor - FTr LCO, however, is only applicable in MODE 1 above 20% of RATED THERMAL POWER. The reasons that this LCO is not applicable below 20% of RATED THERMAL POWER are:

a. Data from the incore detectors are used for determining the measured radial peaking factors. Technical Specification 3.2.3 is not applicable below 20% of RATED THERMAL POWER because the accuracy of the neutron flux information from the incore detectors is not reliable at THERMAL POWER < 20% RATED THERMAL POWER.

b. When core power is below 20% of RATED THERMAL POWER, the core is operating well below its thermal limits, and the Local Power Density (fuel pellet melting) and Thermal Margin/Low Pressure (DNB) trips are highly conservative.

The surveillance requirements for verifying that FTr and Tq are within their limits provide assurance that the actual values of F r and Tq do not exceed the assumed values. Verifying F' after each fuel loading prior to exceeding 70% of RATED THERMAL POWER provides additional assurance that the core was properly loaded. 3/4.2.6 DNB MARGIN The limitations provided in this specification ensure that the assumed margins to DNB are maintained. The limiting values of the parameters in this specification are those assumed as the initial conditions in the accident and transient analyses; therefore, operation must be maintained within the specified limits for the accident and transient analyses to remain valid. MILLSTONE - UNIT 2 B 3/4 2-2 Amendment No. A, s, 7g, 0865 fn, I lip, 280

3/4.10 SPECIAL TEST EXCEPTIONS BASES 3/4.10.1 SHUTDOWN MARGIN This special test exception provides that a minimum amount of CEA worth is immediately available for reactivity control or that the reactor is sufficiently subcritical so as to provide safe operating conditions when tests are performed for CEA worth measurement. This special test exception is required to permit the periodic verification of the actual versus predicted core reactivity condition occuring as a result of fuel burnup or fuel cycling operations. 3/4.10.2 GROUP HEIGHT AND INSERTION LIMITS This special test exception permits individual CEAs to be positioned outside of their normal group heights and insertion limits during the performance of such PHYSICS TESTS as those required to 1) measure CEA worth and 2) determine the reactor stability index and damping factor under xenon oscillation conditions. Millstone - Unit 2 B 3/4 10-1 Amendment No. A 280 0866}}

v t e Letter Sequence Other
TAC:MB6108, Increase the Completion Time When the Core Reactivity Balance is Not within Limit, Consolidate Specification 3.1.5 Actions to Restore Misaligned Ceas, TSTF-67 (Approved, Closed)
Initiation Acceptance... Administration Questions 28 January 2003 Answers Results Approval, Approval Other: ML031050153, ML031710030, ML032691386
MONTHYEAR2003-04-15 [Table View]

ML032691386

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