Text

Amend 148 to License DPR-65,modifying Tech Specs Re cycle- Specific Parameter Limits.Amend Also Adds Core Operating Limits Rept to Definitions Section
	ML20065H068
Person / Time
Site:	Millstone
Issue date:	10/12/1990
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Northeast Nuclear Energy Co (NNECO), Connecticut Light & Power Co, Western Massachusetts Electric Co
Shared Package
ML20065H078	List: ML20065H068; ML20065H081;
References
	DPR-65-A-148 NUDOCS 9010250217
	Download: ML20065H068 (31)
	v • d • e

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/pa aeog[ok UNITED STATES

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'g NUCLEAR REGULATORY COMMISSION 7,,

-l WASHING TON, D. C. 20055

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NORTHEAST NUCLEAR ENERGY COMPANY

.THE CONNECTICUT LIGHT AND POWER C0MPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE WUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 148 License Mo. DPR-65 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated June 26, 1990, as amended by letter dated August 1, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 8.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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2 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-65 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendnient No.148, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/

o y F. Stolz, irector Pr ject Directorate I-4 vision of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: October 12, 1990

ATTACHMENT OF LICENSE AMENDMENT 110.148

[ACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert I

I XVIII XVIII 1-5 1-5 2-2 2-2 2-4 2-4 3/4 1-1 3/4 1-1 3/4 1-3 3/4 1-3 3/4 1-5 3/4 1-5 3/4 1-21 3/4 1-21 3/4 1-22 3/4 1-22 3/4 1-28 3/4 1-28 3/4 1-29 3/4 1/29 3/4 1-30 3/4 1-30 3/4 2-1 3/4 2-1 3/4 2-2 3/4 2-2 3/4 2-3a 3/4 2-3a 3/4 2-4 J/4 2-4 3/4 2-9 3/4 2-9 3/4 2-13 3/4 2-13 3/4 2-14 3/4 2-14 3/4 2-15 3/4 2-15 B 3/4 1-1 B 3/4 1-1 B 3/4 1-2 B 3/4 1-2 B 3/4 1-3 B 3/4 1-3 B 3/4 2-1 B 3/4 2-1 6-19 6-19 6-19(a) 6-19(b) l.

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DEFINITIONS

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SECTION jLA,Q1 I

1. 0 DEFINITIONS m

l Defined Terms................................................

1-1 T h e rm a l Po w e r................................................

1-1 Rat ed Th e rmal Powe r..........................................

1-1 Ope r a t i on al Mod e.............................................

1-1 Action.......................................................

1-1

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. Ope rabl e - Operabil i ty.......................................

1-1 Re p o r t a bl e E v e n t..............................................

1-1 l

q Containment rotegrity........................................

1-2 C h an n el C al i br at i on..........................................

1-2 Channel Check................................................

12 l

Channel Functional Test......................................

1-2 l

Core Alteration..............................................

13-1 i

Shutdown Margin...............................................

1-3 J

Identified' Leakage...........................................

1-3' t

1 Unidentified Leakage.........................................

'l-3 1

a Pressure Boundary Leakage....................................

1-3 1

Controlled Leakage...........................................

1-3 i

Az i mu t h al Powe'r T i l t.........................................

1-4 Dose: Equivalent I-131.........................................

1-4 i

.E-Average.DisintegrationLEnergy..............................

1-4 1

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StaggeredLTest. Basis'.........................................'

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Frequency Notation...........................................

1-4 Axial; Shape Index1............................................

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Core Operating Limits Report.................................-

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ADMINISTRATIVE CNTROLS~

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. 6.9' REPORTING RE001REMENTS 1

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'6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES................

6 17 6.9.2 SPECIAL REPORTS...........................................

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6 6.10 RECORD RETENTION............................................

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6.11 = RADIATION PROTECTION PROGRAM...............................

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6'.12 HIGH RADIATION AREA........................................

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DEFINITIONS AX1AL SHAPE INDEX 1.23 The AXIAL SHAPE INDEX (Yr) used for normal control and indication is the power level detected by thb lower excore nuclear instrument detectors (L) less the power level detected by the upper excore nuclear instrument detectors (U) divided by the sum of these power levels.

The AXIAL SHAPE INDEX (Y,)

used for the trip and pretrip signals in the reactor protection system 1s the above value (Ye) modified by an appropriate multiplier (A) and a constant (B) to determinb the true core axial power distribution for that channel.

LU E

L+U YI - AYE+B Y

CORE OPERATING LIMITS REPORT 1.24 The CORE OPERATING LIMITS REPORT is the unit specific document that provides the core operating limits for the current operating reload cycle.

These cycle specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1.7.

Plant operation within these operating limits is addressed in individual specifications.

ENCLOSURE BVILDING INTEGRITY 1.25 ENCLOSVRE BUILDING INTEGRITY shall exist when:

1.25.1 Each door in each access opening is closed except when the access opening is being used for normal transit entry and exit, and 1.25.2 The enclosure building filtration system is OPERABLE.

REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.

ENGINEERING SAFETY FEATURE RESPONSE TIME 1.27 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of MILLSTONE - UNIT 2 1-5 AmendmentNo.JE,Jys,148 ti

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FIGURE 2.1-1 REACTOR CORE THERMAL MARGIN SAFETY LIMIT - FOUR REACTOR COOLANT PUMPS OPERATING
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TABLE 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS 25 FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
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10 Manual Reactor Trip Not Applicable Not Applicable E
2.
Power Level-High E
Four Reactor Coolant Pumps s 9.6% above THERMAL POWER, s 9.7% Above THERMAL POWER,
1 Operating with a minimum setpoint of with a minimum of s 14.7%
s 14.6% of RATED THERMAL of RATED THERMAL POWER, and n,
POWER.
a maximum of 5 106.7% of RATED THERMAL POWER.
3.
Reactor Coolant Flow -
Low (1) 2 91.7% of reactor coolant 2 90.1% of reactor coolant flow with 4 pumps operating *.
with 4 pumps operating.
4.
Reactor Coolant Pump 2 830 rpm 2 823 rpm Speed - Low 5.
Pressurizer Pressure - High 1 2400 psia s 2408 psia 6.
Containment Pressure - High 5 4.75 psig 5 5.24 psig k!!f 7.
Steam Generator Pressure -
2 680 psia 2 672 psia EL Low (2)
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Design Reactor Coolant flow with 4 pumps operating is the lesser of either:
The reactor coolant flow rate measured per specification 4.2.6.1, or a.
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The minimum value specified in the CORE OPERATING LIMITS REPORT.
E.
3/4.1 REACTVITY CONTROL SYSTEMS 3/4.1.1 REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - T
> 200'F LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be within the limit specified in the CORE i
OPERATING LIMITS REPORT.
APPLICABILITY: MODES 1, 2*, 3 and 4 ACTION:
With the SHUTDOWN MARGIN outside 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 required SHUTOOWN MARGIN is reached.
SURVEILLANCE REQUIREMENT 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be within the limit specified in the CORE OPERATING LIMITS REPORT:
a.
Immediately u)on detection of an inoperable CEA.
If the inoperable CEA is immovaale or untrippable, the SHUTDOWN MARGIN, required by Specification 3.1.1.1, shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable CEA.
b.
When in MODES 1 OR 2, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that CEA group withdrawal is within the Transient Insertion Limits of Specification 3.1.3.6.
c.
Prior to initial operation above 5% RATED THERMAL POWER after each refueling, with the CEA groups at the Transient Insertion Limits of Specification 3.1.3.6.
See Special Test Exception 3.10.1 MILLSTONE - UNIT 2 3/4 1-1 Amendment No. 77, $J 77, 7f,. J77,148
i REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - T,yg i 200'F j
LIMITING CONDITION FOR OPERATION t
3.1.1.2 The SHUTDOWN MARGIN shall be within the limit specified in the CORE OPERATING LIMITS REPORT.
APPLICABillTY: MODE 5.
ACTION:
With the SHUTDOWN MARGIN outside the limit specified in the CORE OPERATING LIMITS REPORT, within 15 minutes initiate and continue boration at 1 40 gpm of boric acid solution at or greater than the required refueling water storage tank (RWST) concentration (ppm) until the required SHUTDOWN MARGIN is restored.
SURVEILLANCE REQUIREMENTS 4.1.1.2 The SHUT 00WN MARGIN shall be determined to be within the limit specified in the CORE OPERATING LIMITS REPORT:
a.
Immediately upon detection of an inoperable CEA.
If the inoperable CEA is immovable or untrippable, the SHUTDOWN MARGIN required by Specification 3.1.1.2 shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable CEA.
b.
At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following factors:
1.
Reactor coolant system t3ron concentration, 2.
CEA position,
3. -
Reactor _ coolant temperature, 4.
Fuel burnup based on gross thermal. energy generation.
5.
-Xenon concentration, and i
6.
Samarium concentration.
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k MILLSTONE-- UNIT'2-3/4 1 AMENDMENT'NO. 148 h
REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT (MTC)
LIMITING CONDITION FOR OPERATION (Continued) 3.1.1.4 The moderator temperature coefficient (MTC) shall be within the j
limits specified in the CORE OPERATING LIMITS REPORT.
The upper limit shall be less than or equal to:
a.
0.7 x 10 4 AK/K/*F whenever THERMAL POWER is s 70% of RATED THERMAL
POWER, b.
0.4 x 10 8 AK/K/'F whenever THERMAL POWER IS > 70% of RATED THERMAL POWER.
APPLICABILITY: MODES 1 and 2*#
ACTION:
With the moderator temperature coefficient outside any one of the above limits, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .
SURVEILLANCE REQUIREMENT 4.1.1.4.1 The MTC shall be determined to be within its limits by confirmatory measurements. MTC measured values shall be extrapolated and/or compensated to permit direct comparision with the predicted values.
'With K,ff 2 1.0.
See Special Test Exemption 3.10.2.
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L MILLSTONE - UNIT 2 3/4 1-S Amendment No. #, fJ, 7f, Jy,148
REACTIVITY CONTROL SYSTEMS ACTION (Continued):
1.
Restored to OPERABLE status within its above specified alignment requirements, or 2.
Declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied After declaring the CEA inoperable, operation in MODES 1 and 2 may continue for up to 7 days per occurrent with a total accumulated time of 1 14 days per calendar year provided all of the following conditions are met:
a.) The THERMAL POWER level shall be reduced to 5 70% of the maximum allowable THERMAL POWER level for the existing Reactor Coolant Pump combination within one hour; if negative reactivity insertion is required to reduce THERMAL POWER, boration shall be used, b.) Within one hour after reducing the THERMAL POWER as required by a), above, the remainder of the CEAs in the group with the inoperable CEA shall be aligned to within 10 steps of the inoperable CEA while maintaining the allowable CEA sequence and insertion limits of Specification 3.1.3.6.
The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation.
c.) The SHUTOOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , e.
With one full length CEA misaligned from any other CEA in its group by 20 steps or more, reduce THERMAL POWER to S 70% of the maximum allowable THERMAL POWER level for the existing Reactor Coolant Pump combination within one hour; if negative reactivity insertion is required to reduce THERMAL POWER, boration shall be used. Within one hour after reducing THERMAL POWER as required above, either:
1.
Restore the CEA to within the above specified alignment requirements, or 2.
Declare the CEA inoperable and determine that the L
SHUTDOWN MARGIN requirements of Specification 3.1.1.1 is l
satisfied. After declaring the CEA inoperable, POWER OPERATION may continue for up to 7 days per occurrence with a total ccumulated time of s 14 days per calendar year provided the remainder of the CEAs in the group wit'h the inoperable CEA are aligned to within 10 steps of the inoperable CEA 1
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MILLSTONE - UNIT 2 3/4 1-21 AMENDMENT N0. 148 L
REACTIVITY CONTROL SYSTEMS ACTION (Continued):
while maintaining the allowable CEA sequence and insertion limits of Specification 3.1.3.6 and the SHUTOOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation.
f.
With more than one full length CEA inoperable or misaligned from any other CEA in its group by 20 steps (indicated position) or more, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .
SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each full length CEA shall be determined to be within 10 steps (indicated position) 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 except during time intervals when the Deviation Circuit and/or CEA Motion inhibit are inoperable, then verify the individual CEA positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .
4.1.3.1.2 Each full length CEA not fully inserted shall be determined to be OPERABLE by movement of at least 10 steps at least once per 31 days.
4.1.3.1.3 The CEA Motion inhibit shall be demonstrated OPERABLE at least once per 31 days by a functional test of the CEA group deviation circuit which verifies that the circuit prevents any CEA from being misaligned from all other CEAs in its group by more than 10 steps (indicated position).
4.1.3.1.4 The CEA Motion Inhibit shall be demonstrated 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 the regulating CEAs from being inserted beyond the Transient Insertion Limits of Specification 3.1.3.6:
Prior to each entry into MODE 2 from MODE 3, except that such a.
verification need not be performed more often than once per 31 days, and b.
At least once per 6 months.
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. MILLSTONE UNIT 2 3/4 1-22 AMENDMENT N0.148 r
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.-. LIMITING CONDITION'FOR OPERATION 4
3.1.3.6 The regulating CEA groups shall be limited to the withdrawal j
l sequence and to the insertion limits specified in the CORE OPERATING LIMITS REPORT.
Regulating CEAs are considered to be fully withdrawn when withdrawn
- to at least 176 steps. CEA insertion between the Long Term Steady State Insertion Limits and the Transient Insertion Limits is restricted to the limits specified in the CORE OPERATING LIMITS REPORT.
APPLICABILITY: MODES 1* and 2*#,
ACTION:
a.
With the regulating CEA groups inserted beyond the Transient Insertion Limits specified in the CORE OPERATING LIMITS REPORT, l
except for surveillance testing pursuant to Specification 4.1.3.1.2, within two hours either:
1.
Restore the regulating CEA groups to within the limits, or 2.
Reduce THERMAL POWER to that fraction of RATED THERMAL POWER which is allowed by the CEA group position using the above figures.
i b.
With the regulating CEA groups inserted between the Long Term Steady State Insertion Limits and the Transient Insertion Limits specified in the CORE OPERATING LIMITS REPORT for intervals l
> 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, except during operation pursuant to
.the provisions of ACTION items c. and d. of Specification 3.1.3.1,-
operation may proceed provided either:
t 1.
The Short Term Steady State Insertion Limits specified in the CORE OPERATING LIMITS REPORT are not exceeded, or 1
2.
Any subsequent increase in THERMAL POWER is restricted to f5 5%Lof_ RATED THERMAL POWER per hour.
7 See Special Test Exception 3.10.2 and 3.10.5.
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MILLSTONE-UNIT:2
.3/4'l-28 AMENDMENT N0.-148 g.
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d REACTVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
With the regulating CEA groups inserted between the Long Term Steady c.
State Insertion Limits and the Transient Insertion Limits specified in the CORE OPERATING LIMITS REPORT for intervals > 5 EFPD per 30 EFPD interval or > 14 EFPD per calendar year, except during operations pursuant to the provisions of ACTION items c. and d. of Specification 3.1.3.1, either:
1.
Restore the regulating groups to within the Long Term Steady State Insertion Limits specified in the CORE OPERATING LIMITS REPORT within two hours, or 2.
Be in HOT STANDBY within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .
SURVEILLANCE REQUIREMENTS 4.1.3.6 The position of each regulating CEA group shall be determined to be 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 except during time intervals when the PDIL Auctioneer Alarm Circuit is inoperable, then verify the individual CEA positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The accumulated times during which the regulatory CEA groups are inserted between the Long Term Steady State Insertion Limits and the Transient Insertion Limits specified in the CORE OPERATING LIMITS REPORT shall be determined at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
1 MILLSTONE - UNIT 2 3/4 1-29 AMENDMENT N0. 148 1
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~ LINEAR HEAT-RATE LIMITING CONDITION FOR OPERATION (Continued) 3.2.1 The linear heat rate, including heat generated in the fuel, clad and moderator, shall not exceed the limits specified in the CORE OPERATING LlHITS REPORT.
APPLICABILITY: MODE 1.
ACTION:
During operation with the linear heat rate being monitored by the Incore Detector Monitoring System, comply with the following ACTION:
With-the linear heat rate exceeding the limit as indicated by four or more coincident incore channels, within 15 minutes initiate corrective action to reduce the linear heat rate to less than or equal to the limit and either:
1 Restore the linear heat rate to less than or equal to the limit a.
within one hour, or b.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .
-During' operation with the linear heat rate being monitored by the Excore Detector Monitoring System, comply with the following ACTIONS:
-l With-the linear heat rate exceeding its limit, as indicated by the AXIAL SHAPE INDEX being-outside of the power dependent limits on the Power Ratio Recorder, either:
-l Restore the AX1Al. SHAPE INDEX to within the limits specified in the a.
CORE OPERATING LIMITS REPORT within I hour from initially exceeding-the linear heat rate limit.or l\\
b.
Be in at least HOT-STANDBY within.the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .
SURVEILLANCE REQUIREMENT-4. 2. 1. 11 - The linear heat' rate shall be determined to begwithin=its limits by
. continuously monitoring'the core power. distribution with either the excore
.i detector monitoring system.or.with the.'incore detector monitoring system.
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, POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENT (Continued) 4.2.1.2 Excore Detector Monitorino System - The excore detector monitoring system may be used for monitoring the core power distribution by:
Verifying at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months that the full length CEAs are a.
withdrawn to 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.
i I
4.2.1.3 Incore Detector Monitorino System - The incore detector monitoring system may be used for monitoring the core power distribution by verifying that the incore detector Local Power Density alarms:
Are adjusted to satisfy the requirements of the core power a.
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 limit when the factors specified in the CORE OPERATING LIMITS REPORT are appropriately included in the setting of these alarms.
l MILLSTONE - UNIT 2 3/4 2-2 AmendmentNo.27,JEff,99, 179 ' N
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s POWER DISTRlWJ,10N LIMITI T
TOTAL INTEC MTED RADIAL PEAKING FACTOR F
y llMITING C)NDITION FOR OPERATION T
T 3.2.3 The calculated value of F defined as F
=F (1+T ), shall be within the limit specified in the CORE OP[ RATING LIMITS REPORT.
4 r
APPLICABillII: MODE 1*.
ACJJQN:
T With F exceeding its limit within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either:
7 a.
R duce THERMAL POWER to bring the combination of THERMAL POWER and F to within the limit and withdraw the full length CEAs to or b yond the Long Term Steady State Insertion Limits of Specification 3.1.3.6; or b.
Be in at least HOT STANDBY.
SURVEILL ANCE REQUIREMENT 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.
4.2.3.2 F shall be celculated by the expression FT=F 1T shall T
T be determined to be within its limit at the followin6 intErv(a+ls?) and 7
n.
Prior to operation above 70 per?ent of RATED THERKAL POWER after each fuel loading, b.
At least once per 31 dsys of accumulated operation in Mode 1, and c.
Within four hours if the AXIMUTHAL POWER TILT (T ) is > 0.020, q
T 4.2.3.3 F shall be determined each time a calculation of F is required by 7
usingthe1Ecoredetectorstoobtainapowerdistributionmapwithallfull length CEAs at or above the Long Term Steady State Insertion Limit for the existing. Reactor Coolant Pump Combination.
T 4.2.3.4 i shall be determined en9h time a calculation of F is required and thevalueofT used to determine F shallbethemeasuredvaiueofT.
q r
q
See Special Test Exception 3.10.2 4
V MILLSTONE UNIT 2 3/4 2 9 Amendment No. 75,52,77,)#,
99, 111, 159, 148
. x
EQELRDISTRIBUTIONLIMITS DNB MARGIN LIMITING CONDITION FOR OPERATION 3.2.6 The DNB margin shall be temperature, pressurizer pressure, preserved by maintaining the cold leg reactor coolant flow rate, and AXIAL SHAPE INDEX within the limits specified in the CORE OPERATING LIMITS REPORT.
APPLICABILITY:
MODE 1.
ACTION:
With any of the above parameters exceeding its specified limits, restore the parameter to within its above specified limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to s 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .
SURVEILLANCE REQUIREMENTS 4.2.6.1 The cold leg temperature, pressurizer pressure, and AX1AL SHAPE INDEX shall be determined to be within the limits s OPERATING LIMITS REPORT at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .pecified in the LORE The reactor coolant flow rate shall be determined to be within the limit specified in the CORE OPERATING LIMITS REPORT at least once per 31 days.
4.2.6.2 The provisions of Specification 4.0.4 are not applicable.
MILLSTONE - UNIT 2 3/4213 Amendment No. JS, SS, JJJ, 148 l
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- Amendment No.-)), M, 7),
't 79.JU,JU,148 l
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v LMI.LLSTONE - UNIT (2;
3/4=2 15-AMENDMENT NO.-148-ym o,u 4 u
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3/4.1 REACTIVITY CONTROL SYSTEMS BASES l
3/4.1.1 P3 RATION CONTROL j
314.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within i
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 o depletion, RCS boron concentration, and RCS T' $.
The most restrictive condition occurs at EOL, with T at no load erating temperature, and is uncontrolled RCS cooldown. associated with a postulated stl 8 line break acc In the analysis of this accident, the minimum SHUTDOWN MARGIN specified in the CORE OPERATING LIMITS REPOR required by Specification 3.1.1.1 is based upon this lim l
consistent with FSAR accident analysis assumptions.
during the fuel cycle, this value is conservative. With TFor earlier periods the reduced SHUTDOWN MARGIN sreactivity transients resulting from any s 200'F, the provides adequate protection.pecified in the CORE OPERATING LIMITS REPORT 3/4.1.1.3 BORON DILUTION AND ADDITION A minimum flow rate of at least 3000 GPM provides adequate mixing, prevents boron concentration changes in the Reactor Coolant System least 3000 GPM will circulate an equivalent Reactor Coolant System volume ofA 10,060 + 700/ 0 cubic feet in approximately 30 minutes. The reactivity cha for operator recognition and control. rate associated with boron concentr 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.
surveillance requirements for measurement of the MTC during each fuel cycle The principally to the reduction in RCS boron concentration as i
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.
l MILLSTONE - UNIT 2 B 3/4 1 1 Amendment No. US,148
REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1.5 MINIMUM TEMPERATURE FOR CRITICALITY The MTC is expected to be slightly negative at operating conditions.
However, at the beginning of the fuel cycle, the MTC may be slightly positive at operating conditions and since it will become more positive at lower temperatures, this specification is provided to restrict reactor operation when T,yg is significantly below the normal operating tempera-ture.
3/4.1.2 BORAT10N SYSTEMS l
The boron injection system ensures that negative reactivity control is available during each mode of facility operation.
The components required to perform this function include 1) borated water sources, 2) charging pumps, 3) separate flow paths, 4) boric acid pumps, and 5) an emergency power supply from OPERABLE diesel generators.
With the RCS average temperature above 200'F, a minimum of two separate and redundant boron injection flowpaths are provided to ensure single functional capability in the event an assumed failure of a pump or valve rende's one of the flowpaths inoperable.
Redundant flow paths from the Boric 1.cid Storage Tanks are achieved through Boric Acid Pumps, gravity feed lines and Charging Pumps.
Redundant flow paths from the Refueling Water Storage Tank are achieved through Charging Pump flow path guaranteed by Technical Specification 3.1.2.2 and the HPSI flow path guaranteed by Technical Specification 3.5.2 and 3.5.3.
Allowable out of-service periods ensure that minor component repair or corrective action may be completed without undue risk to overall facility safety from injection system failures during the repair period.
The minimum boration capability is sufficient to provide a SHUTDOWN MARGIN within the limits specified in the CORE OPERATING LIMITS REPORT at all temperatures above 200'F.
The maximum boration capability requirement occurs at EOL from full power equilibrium xenon conditions and requires an equivalent of 4900 gallons of 3.5% boric acid solution from the boric acid tanks plus 15,000 of 1720 ppm borated water from the refueling water storage tank. The refueling water storage tank can also be used alone by feed and-bleed using well under the 370,000 gallons of 1720 ppm borated water required.
The requirements for a minimum contained volume of 370,000 gallons of borated water in the refueling water storage tank ensures the capability for borating the RCS to the desired level.
The specified quantity of I
borated water is consistent with the ECCS requirements of Specification 3.5.4.
Therefore, the larger volume of borated water is specified here too.
MILLSTONE - UNIT 2 B 3/4 1 2 Amendment No. JE, JJ, JJJ,148 a
BASES 3/4.1_._2 P_0PATION SYSTEMS (Continued)
The analysis to determine the boration requirements assumed that the Reactor Coolant System is borated concurrently with cooldown, in the limiting situation when letdown is not available, the cooldown is assumed to be initiated within 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months and cooldown to 220'F, is completed in the next 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months .
With the RCS temperature below 200'F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity change in the event the single injection system becomes inoperable.
The boron capability required below 200'F is based upon providing a SHUTDOWN MARGIN within the limit specified in the CORE OPERATING LIMITS REPORT at 140'F after xenon decay.
This condition requires either 3750 gallons of 2.5% boric acid solution from the boric acid tanks or 57,300 gallons of 1720 ppm borated water from the refueling water storage tank.
The maximum boron concentration requirement (3.5%) and the minimum temperature requirement (55'F) for the Boric Acid Storage Tank ensures that boron does not precipitate in the Boric Acid System.
The daily surveillance requirement provides sufficient assurance that the temperature of the tank will be maintained higher than 55'F at all times.
A minimum boron concentration of 1720 ppm is required in the RWST at all times in order to satisfy safety analysis assumptions for boron dilution incidents and other transients using thL RWST as a borated water source as well as the analysis assumption to determine the boration requirement to ensure adequate shutdown margin.
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, l
The ACTION statements applicable to an immovable or untrippable CEA and to a large misalignment (1 20 steps) of two or more CEAs, require e prompt shutdown of the reactor since either MILLSTONE UNIT 2 B 3/4 1-3 Amendment No. 75,51,71,JJE,
)),J19,148
3/4.2 POWER DISTRIBUTION tlMITS i
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 2200*F.
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 verify-ing that the linear heat rate does not exceed its limits.
The Excore Detector Monitoring System performs this function by continuously monitoring the AX1AL SHAPE INDEX with two OPERABLE excore neutron flux detectors and verifying that the AX1AL 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 i
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 3.1.3.2, 3.1.3.S and 3.1.3.6 are satisfied, 2) the flux peaking augmentation factors are as specified in the CORE OPERATING LIMITS REPORT,
3) the AZIMUTHAL POWER TILT restrictions of Specification 3.2.4 are satisfied, l
and 4) the Total 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 LlHITS REPORT.
The setpoints for these alarms include allowances, set in the conservative directions as specified in the CORE OPERATING LIMITS REPORT.
3/4.2.3 and 3/4.2.4 TOTAL INTEGRATED RADIAL PEAKING FACTORS FT AND AZIMUTHAL POWER TILT - T r
q The limitations on FT tionsusedintheanalysi[andT are provided to 1) ensure that the assump-fore 9tablishingtheLinearHeatRateandLocal 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 ONB Margin LCO, and Thermal Margin /LowPressureLSSSsetpointsremainvaliddur{ngoperationatthe various allowable CEA group insertion limits.
If F or i exceed their basic limitations,operationmaycontinueundertheadditionalfestrictionsimposed 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 MILLSTONE - UNIT 2 B 3/4 2 1 Amendment No. 75, 52, JJ2, J;p,148 l
e
ADMINISTRATIVE CONTROLS,
i d.
Documentation of all failures (inability to lift or reclose within the tolerances allowed by the design basis) and challenges to the pressurizer PORVs or safety valves.
MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of cperating statistics and shutdown experience shall be submitted on a monthly basis to the U.S.
Nuclear Regulatory Commission, i
Document Control Desk, Washington, D.C.
20555, one copy to the Regional 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 6.9.1.7 4.
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 T
3/4.1.1.2 SHUTDOWN MARGIN - T vg > 200'F a
s 200'F 3/4.1.1.4 ModeratorTemperatufl9 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 r
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)
XN7527(A),
latest Revisions and Supplements,
' Exxon Nuclear Neutronics Design Methods for Pressurized Water Reactors,' Exxon Nuclear Company.
2)
XNNF8473(P),
latest Revision and Supplements.
" Exxon Nuclear Methodology for Pressurized Water Reactors:
Analysis of Chapter 15 Event," Exxon Nuclear Company.
3)
XN NF 82-21(A),
latest devision and Supplements,
' Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations,' Exxon Nuclear Company.
4)
XN84-93(A), latest Revision and Supplements, 'Steamline Break Methodology for PWR's, Exxon Nuclear Company.
5)
XN 75 32(A), Supplements 1, 2,
3, and 4
' Computational Procedure for Evaluation Rod Bow,' Exxon Nuclear Company.
6)
XN NF 82 49(A),
latest Revision,
' Exxon Nuclear Company Evaluation Model EXEM PWR Small Break Model,' Exxon Nuclear Company.
MILLSTONE - UNIT 2 6 19 Amendment Nos. JS, JJ. 194, 111,11),119 12#, JJJ.148, l
l
\\
' ADMINISTRATIVE CONTROLS 7)
EXEM PWR Large Break LOCA Evaluation Model as defined by:
XN NF 82 20(A),
latest Revision and Supplements.
Exxon Nuclear Company Evaluation Model EXEM/PWR ECCS Model Updates,' Exxon Nuclear Company.
XN NF 82-07(A), latest Revision.
Exxon Nuclear Company ECCS Cladding Swelling and Ruoture Model,' Exxon Nuclear Company.
XNNF81-58(A),
latest
Revision,
'RODEX2 Fuel Rod Thermal Mechanical Response Evaluation Model,' Exxon Nuclear Company.'
XN NF 8516(A), Volume 1 and Supplements, Volume 2 latest Revision and Supplements. *PWR 17x17 Fuel Cooling Test Program,' Exxon Nuclear Company.
XNNF-85105(A), and Supplements, ' Scaling of FCTF Based Reflood Heat Transfer Correlation for Other Bundle Designs,*
Exxon Nuclear Company, 8)
XN NF 78 44(A),
latest
Revision,
' Generic Control Rod c
Ejection Analysis,' Exxon Nuclear Company.
9)
XN NF-621(A),
latest Revision,
'XNB Critical Heat Flux Correlation,' Exxon Nuclear Company.
The acceptable Millstone 2
specific application of these analytical methodologies are described in ANF 88126, ' Millstone Unit 2 Cycle 10 Safety Analysis Report,' dated October,1988.
c.
The core operating limits shall be determined so that all applicable limits e.g.,
fuel themal mechanical Itmits, core thermal-hydraulic l(imits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
d.
The CORE OPERATING LIMITS REPORT, including any mid cycle revisions or supplements
thereto, shall be provided upon issuance, for en:h reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C.
20555, one copy to the Regional Administrator, Region 1, and one copy to the NRC Resident Inspector within the time period saecified for each report.
These reports shall be submitted covering the act' vities identified below pursuant to the requirements of the applicable reference specification:
Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.
a.
b.
Inoperable Metcorological Monitoring Instrumentation, Specifi-cation 3.3.3.4.
MILLSTONE - UNIT 2 6 19(a)
AMENDMENT NO.148 J
ADMINISTRATIVE CONTROLS c.
Safety Class 1
Inservice Inspection Program
Review, Specification 4.4.10.1.
d.
ECCS Actuation, Specifications 3.5.2 and 3.5.3.
e.
Fire Detection Instrumentation Specifications 3.3.3.7.
f.
Fire Suppression Systems, Specifications 3.7.9.1 and 3.7.9.2.
g.
RCS Overpressure Mitigation, Specification 3.4.9.3 h.
Radiological Effluent Reports required by Specifications 3.11.1.2, 3.11.2.2, 3.11.2.3 and 3.11.4.
i.
Degradation of containment structure, Specification 4.6.1.6.4.
j.
Steam Generator Tube Inspection, Specification 4.4.5.1.5.
k.
Accident Monitoring Instrumentation, Specification 3.3.3.8.
1.
Radiation Monitoring Instrumentation, Specification 3.3.3.1.
m.
Reactor Coolant System Vents, Specification 3.4.11.
MILLSTONE - UNIT 2 6-19(b)
AMENDMENT NO 148
.

ML20065H068

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