Text

Technical Specification, Issuance of Amendment, Relocation of Technical Specification Parameters to the Core Operating Limits Report
	ML040700311
Person / Time
Site:	Millstone
Issue date:	03/09/2004
From:	Nerses V; NRC/NRR/DLPM/LPD1
To:	Christian D; Dominion Nuclear Connecticut
References
	TAC MB8387
	Download: ML040700311 (19)
	v • d • e

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY .................................................... 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL Shutdown Margin - MODES I AND 2 .................................................... 3/4 1-1 Shutdown Margin - MODES 3,4, AND 5 LOOPS FILLED ........................ 3/4 1-3 FIGURE 3.1-1 DELETED .................................................... 3/4 1-4 FIGURE 3.1-2 DELETED .................................................... 3/4 1-5 FIGURE 3.1-3 DELETED ..................................................... 3/4 1-6 FIGURE 3.1-4 DELETED .................................................... 3/4 1-7 Shutdown Margin - Cold Shutdown -

Loops Not Filled ..................................................... 3/4 1-8 FIGURE 3.1-5 DELETED ..................................................... 3/4 1-9 Moderator Temperature Coefficient............................................................3/4 1-10 Minimum Temperature for Criticality .................................................... 3/4 1-12 3/4.1.2 BORATION SYSTEMS DELETED ...... 3/4 1-13 DELETED ...... 3/4 1-14 DELETED ...... 3/4 1-15 DELETED ...... 3/4 1-16 DELETED ...... 3/4 1-17 DELETED ...... 3/4 1-18 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height ........ 3/4 1-20 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL-LENGTH ROD ...................... 3/4 1-22 Position Indication Systems - Operating ......................................... 3/4 1-23 MILLSTONE - UNIT 3 iv Amendment No. M, 60,99, A, I--, 218

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE DELETED ....................................... 3/4 1-24 Rod Drop Time ....................................... 3/4 1-25 Shutdown Rod Insertion Limit ....................................... 3/4 1-26 Control Rod Insertion Limits ....................................... 3/4 1-27 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE ....................................... 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - FQ(Z) ....................................... 3/4 2-5 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR..................................................................................3/4 2-19 3/4.2.4 QUADRANT POWER TILT RATIO ......................... 3/4 2-24 3/4.2.5 DNB PARAMETERS ......................... 3/4 2-27 TABLE 3.2-1 DELETED ......................... 3/4 2-28 I 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION .................................... 3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION .................................... 3/4 3-2 TABLE 3.3-2 DELETED TABLE 4.3-I REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS .................................................. 3/43-10 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION .................................................. 3/4 3-15 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION .................................................. 3/4 3-17 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS ................................................ 3/4 3-26 MILLSTONE - UNIT 3 v Amendment No. 9,69, 60, 89-1, 2O 2, 218

TABLE 2.2-4 (Continued)

TABLE NOTATIONS r NOTE I :OVERTEMPERATURE AT o AT (1l +'s) K2(1 + (T -)+K3(P-P')- f (AI) i Where: AT is measured Reactor Coolant System AT, 0 F; ATo is loop specific indicated AT at RATED THERMAL POWER, 0F; (1 + rIs)

(I + T22 s) is the function generated by the lead-lag compensator on measured AT;

Tj and T2 are the time constants utilized in the lead-lag compensator for AT, T, 2 [*] sec, T2 < [*] sec; K2 2 (*]/OF; (1It 4 ) is the function generated by the lead-lag compensator for Tavg; T4 and T5 are the time constants utilized in the lead-lag compensator for Tavg, T4 2 [*] sec, Ts[*] sec; T is measured Reactor Coolant System average temperature, OF; T' is loop specific indicated Tavg at RATED THERMAL POWER, < [*]0 F; K3 2 [*]/psi 0 P is measured pressurizer pressure, psia; P' is nominal pressurizer pressure, 2 [*] psia; s is the Laplace transform operator, sec-1 ;

(The values denoted with [$] are specified in the COLR.)

0:

r. TABLE 2.2-1 (Continued) ci, r

TABLE NOTATIONS 0

z NOTE 1: (Continued) and f1 (Al) is a function of the indicated difference between top and bottom detectors of the power range neutron ion i chambers; with nominal gains to be selected based on measured instrument response during plant startup tests calibrations such that:

(1) For qt - qb between [*]% and [*]%, fl, (Al) Ž [*], where qt and qb are percent RATED THERMAL POWER in I the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RATED THERMAL POWER;

!,3 0 (2) For each percent that the magnitude of qt - qb exceeds [*]%, the AT Trip Setpoint shall be automatically reduced by 2 [*]% of its value at RATED THERMAL POWER. I (3) For each percent that the magnitude of qt - qb exceeds [*]%, the AT Trip Setpoint shall be automatically reduced by 2 [*]% of its value at RATED THERMAL POWER. I NOTE 2: The maximum channel as left trip setpoint shall not exceed its computed trip setpoint by more than the following:

(1) 0.4% AT span for the AT channel 30 (2) 0.4% AT span for the Tavg channel 0

(3) 0.4% AT span for the pressurizer pressure channel (4) 0.8% AT span for the f(AI) channel z

0 (The values denoted with [*] are specified in the COLR.) I co

TABLE 2.2-1 (Continued)

TABLE NOTATTONS i NOTE 3: OVERPOWER AT i (LT (l +rT) <K 4 - K5 (l+Ts)T-K 6 (T- T")

Y~.TQ) (1 + 2 s) (+ t 7 s w Where: AT is measured Reactor Coolant System AT, 0 F; ATo is loop specific indicated AT at RATED THERMAL POWER, 0F; (I +'r 1 s)

(1 + as) is the function generated by the lead-lag compensator on measured AT;

'rl and r2 are the time constants utilized in the lead-lag compensator for AT, T, 2 [*1 sec, T2 S [*] sec; K4 :5 [$]; I K5 Ž[*]/oF for increasing Tavg and Ks [*] for decreasing Tavg; (Tr7S)

( +T S) is the function generated by the rate-lag compensator for Tavg;

'r7 is the time constant utilized in the rate-lag compensator for Tavg, r 7 > [*] sec; 3l T is measured average Reactor Coolant System temperature, OF; z T" is loop specific indicated Tavg at RATED THERMAL POWER, < [*]IF; K6 2 [*]/IF when T > T" and K6 < [*]/IF when T

T";

s is the Laplace transform operator, secl; (The values denoted with [*] are specified in the COLR.)

co

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1.1 BORATION CONTROL SHUTDOWN MARGIN - MODES 1 AND 2 LIMITING CONDITION FOR OPERATION 3.1.1.1.1 The SHUTDOWN MARGIN shall be within the limits specified in the Core Operating Limits Report (COLR).

APPLICABILITY: MODES I and 2*.

ACTION:

With the SHUTDOWN MARGIN not within the limits specified in the COLR, immediately initiate and continue boration at greater than or equal to 33 gpm of a solution containing greater than or equal to 6600 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be within the limits specified in the COLR:

a. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod(s) is inoperable. If the inoperable control rod is immovable or untrippable, the above required SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod(s);

b. When in MODE 1 or MODE 2 with Keffgreater than or equal to I at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that control bank withdrawal is within the limits of Specification 3.1.3.6;

c. When in MODE 2 with Keff less than 1, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to achieving reactor criticality by verifying that the predicted critical control rod position is within the limits of Specification 3.1.3.6;

d. Prior to initial operation above 5% RATED THERMAL POWER after each fuel loading, by consideration of the factors of Specification 4.1.1.1.2, with the control banks at the maximum insertion limit of Specification 3.1.3.6; and

See Special Test Exceptions Specification 3.10.1.

MILLSTONE - UNIT 3 3/4 1-1 Amendment No. 604-3 2l4-7..218

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - MODES 3.4 AND 5 LOOPS FILLED LIMITING CONDITION FOR OPERATION 3.1.1.1.2 The SHUTDOWN MARGIN shall be within the limits specified in the Core Operating Limits Report (COLR).*

APPLICABILITY: MODES 3,4 and 5 ACTION:

With the SHUTDOWN MARGIN less than the required value, immediately initiate and continue boration at greater than or equal to 33 gpm of a solution containing greater than or equal to 6600 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.1.2.1 The SHUTDOWN MARGIN shall be determined to be within the limits specified in the COLR:

a. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod(s) is inoperable. If the inoperable control rod is immovable or untrippable, the above required SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod(s); and

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:

I. Reactor Coolant System boron concentration,

2. Control rod position,

3. Reactor Coolant System average temperature,

4. Fuel burnup based on gross thermal energy generation,

5. Xenon concentration, and

6. Samarium concentration.

4.1.1.1.2.2 Valve 3CHS-V305 shall be verified closed and locked at least once per 31 days.

Additional SHUTDOWN MARGIN requirements, if required, are given in Specification 3.3.5.

MILLSTONE - UNIT 3 3/4 1-3 Amendment No. 69, X-, 164, 2a, 218

THIS PAGE INTENTIONALLY LEFT BLANK MILLSTONE - UNIT 3 3/4 14 Amendment No. X, -,9, -,60, 4-64, i-2-, 218

THIS PAGE INTENTIONALLY LEFT BLANK MILLSTONE - UNIT 3 3/4 1-6 Amendment No. 60,464, 218

THIS PAGE INTENTIONALLY LEFT BLANK MILLSTONE - UNIT 3 3/4 1-7 Amendment No. 60, -64, 218

REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - COLD SHUTDOWN - LOOPS NOT FILLED LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to

a. the limits specified in the CORE OPERATING LIMITS REPORT (COLR) for MODE 5 with RCS loops not filled* or

b. the limits specified in the COLR for MODE 5 with RCS loops filled* with the chemical and volume control system (CVCS) aligned to preclude reactor coolant system boron concentration reduction.

APPLICABILITY: MODE 5 LOOPS NOT FILLED ACTION:

a. With the SHUTDOWN MARGIN less than the above, immediately initiate and continue boration at greater than or equal to 33 gpm of a solution containing greater than or equal to 6600 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

b. With the CVCS dilution flow paths not closed and secured in position in accordance with Specification 3.1.1.2(b), immediately close and secure the paths or meet the limits specified in the COLR for MODE 5 with RCS loops not filled.

SURVEILLANCE REQUIREMENTS 4.1.1.2.1 The SHUTDOWN MARGIN shall be determined to be within the limits specified in the COLR:

a. Within I hour after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod(s) is inoperable. If the inoperable control rod is immovable or untrippable, the SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod(s); and

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:

I. Reactor Coolant System boron concentration,

2. Control rod position,

3. Reactor Coolant System average temperature,

4. Fuel burnup based on gross thermal energy generation,

Additional SHUTDOWN MARGIN requirements, if required, are given in Specification 3.3.5.

MILLSTONE - UNIT 3 3/4 1-8 Amendment No. 60, 99, 443,44-, 218

THIS PAGE INTENTIONALLY LEFT BLANK MILLSTONE - UNIT 3 3/4 1-9 Amendment No. 60, 99, 64, 218

POWER DISTRIBUTION LIMITS 3/4.2.5 DNB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DNB-related parameters shall be maintained within the limits specified in the CORE OPERATING LIMITS REPORT (COLR):

a. Reactor Coolant System T.yg, and

b. Pressurizer Pressure.

APPLICABILITY: MODE 1.

ACTION:

With any of the above parameters exceeding its limit, restore the parameter to within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to less than 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 4.2.5 Each of the above DNB-related parameters shall be verified to be within the limits specified in the COLR at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

MILLSTONE - UNIT 3 3/4 2-27 Amendment No. -, 60, 218

THIS PAGE INTENTIONALLY LEFT BLANK MILLSTONE - UNIT 3 3/4 2-28 Amendment No. 4X2, 69, 2-1, 218

INSTRUMENTATION 314.3.5 SHUTDOWN MARGIN MONITOR LIMITING CONDITION FOR OPERATION 3.3.5 Two channels of Shutdown Margin Monitors shall be OPERABLE

a. With a minimum count rate as designated in the CORE OPERATING LIMITS REPORT (COLR), or

b. If the minimum count rate in Specification 3.3.5.a cannot be met, then the Shutdown Margin Monitors may be made operable with a lower minimum count rate, as specified in the COLR, by borating the Reactor Coolant System above the requirements of Specification 3.1.1.1.2 or 3.1.1.2. The additional boration shall be:

1. A minimum of 150 ppm above the SHUTDOWN MARGIN requirements specified in the COLR for MODE 3, or

2. A minimum of 350 ppm above the SHUTDOWN MARGIN requirements specified in the COLR for MODE 4, MODE 5 with RCS loops filled, and MODE 5 with RCS loops not filled.

APPLICABILITY: MODES 3*, 4, and 5.

ACTION:

a. With one Shutdown Margin Monitor inoperable, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b. With both Shutdown Margin Monitors inoperable or one Shutdown Margin Monitor inoperable for greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , immediately suspend all operations involving positive reactivity changes via dilution and rod withdrawal.

Vcrify the valves listed in Specification 4.1.1.2.2 are closed and secured in position within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and at least once per 14 days thereafter.**

Verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1.2 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

The shutdown margin monitors may be blocked during reactor startup in accordance with approved plant procedures.

- The valves may be opened on an intermittent basis under administrative controls as noted in Surveillance 4.1.1.2.2.

MILLSTONE - UNIT 3 3/4 3-82 Amendment No. 1-64, 2417, 218

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1.1 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 the following reactivity conditions is met; either:

a. A Keff of 0.95 or less, or

b. A boron concentration of greater than or equal to the limit specified in the CORE OPERATING LIMITS REPORT (COLR).

Additionally, the CVCS valves of Specification 4.1.1.2.2 shall be closed and secured in position.

APPLICABILITY: MODE 6.*

ACTION:

a. With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 33 gpm of a solution containing greater than or equal to 6600 ppm boron or its equivalent until Keff is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to the limit specified in the COLR, whichever is the more restrictive.

b. With any of the CVCS valves of Specification 4.1.1.2.2 not closed** and secured in position, immediately close and secure the valves.

SURVEILLANCE REQUIREMENTS 4.9.1.1.1 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 full-length control rod in excess of 3 feet from its fully inserted position within the reactor vessel.

4.9.1.1.2 The boron concentration of the Reactor Coolant System and the refueling cavity shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

4.9.1.1.3 The CVCS valves of Specification 4.1.1.2.2 shall be verified closed and locked at least once per 31 days.

The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

- Except those opened under administrative control.

MILLSTONE - UNIT 3 3/4 9-1 Amendment No. R, 60,99, A-3, I203, 218

ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORTS 6.9.1.5 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis 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, no later than the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITS REPORT 6.9.1.6 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 for the following:

1. Overtemperature AT and Overpower AT setpoint parameters for Specification 2.2.1,

2. Shutdown Margin for Specifications 3/4.1.1.1.1, 3/4.1.1.1.2, and 3/4.1.1.2,

3. Moderator Temperature Coefficient BOL and EOL limits and 300 ppm surveillance limit for Specification 3/4.1.1.3.

MILLSTONE - UNIT 3 6-19a Amendment No. 24, 3-7, 69, 6, , 218

ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Cont.)

4. Shutdown Rod Insertion Limit for Specification 3/4.1.3.5,

5. Control Rod Insertion Limits for Specification 3/4.1.3.6,

6. Axial Flux Difference Limits, target band, and APLND for Specifications 3/4.2.1.1 and 3/4.2.1.2,

7. Heat Flux Hot Channel Factor, K(z), W(z), APLND, and W(Z)BL for Specifications 3/4.2.2.1 and 3/4.2.2.2.

8. Nuclear Enthalpy Rise Hot Channel Factor, Power Factor Multiplier for Specification 3/4.2.3.

9. DNB Parameters for Specification 3/4.2.5.

10. Shutdown Margin Monitor minimum count rate for Specification 3/4.3.5.

11. Boron Concentration for Specification 3/4.9.1.1.

6.9.1.6.b The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:

1. WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," (&L Proprietary). (Methodology for Specifications 3.1.1.3--Moderator Temperature Coefficient, 3.1.3.5--Shutdown Bank Insertion Limit, 3.1.3.6--Control Bank Insertion Limits, 3.2.1--Axial Flux Difference, 3.2.2--Heat Flux Hot Channel Factor, 3.2.3--Nuclear Enthalpy Rise Hot Channel Factor,3.1.1.1.1, 3.1.1.1.2, 3.1.1.2 - Shutdown Margin,3.9.1.1 -- Boron Concentration.)

2. T. M. Anderson to K. Kniel (Chief of Core Performance Branch, NRC), January 31, 1980--

Attachment:

Operation and Safety-Analysis Aspects of an Improved Load Follow Package.

3. NUREG-800, Standard Review Plan, U.S. Nuclear Regulatory Commission, Section 4.3, Nuclear Design, July 1981 Branch Technical Position CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC), Revision 2, July 1981.

4. WCAP-10216-P-A-RIA, "RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION,"

(W Proprietary). (Methodology for Specifications 3.2.1--Axial Flux Difference

[Relaxed Axial Offset Control] and 3.2.2--Heat Flux Hot Channel Factor [W(z) surveillance requirements for FQ Methodology].)

5. WCAP-9561-P-A, ADD. 3, "BARTA-I: A COMPUTER CODE FOR THE BEST ESTIMATE ANALYSIS OF REFLOOD TRANSIENTS--SPECIAL REPORT:

THIMBLE MODELING W ECCS EVALUATION MODEL," (W Proprietary). (Methodology for Specification 3.2.2--Heat Flux Hot Channel Factor.)

6. WCAP-10266-P-A, Addendum 1, "THE 1981 VERSION OF THE WESTINGHOUSE ECCS EVALUATION MODEL USING THE BASH CODE,"

(W Proprietary). (Methodology for Specification 3.2.2--Heat Flux Hot Channel Factor.)

MILLSTONE - UNIT 3 6-20 Amendment No. 24, 3, 60, 69, S+,

40,4,70, 218

ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Cont.)

7. WCAP-1 1946, "Safety Evaluation Supporting a More Negative EOL Moderator Temperature Coefficient Technical Specification for the Millstone Nuclear Power Station Unit 3," (W Proprietary).

8. WCAP-10054-P-A, "WESTINGHOUSE SMALL BREAK ECCS EVALUATION MODEL.17 USING THE NOTRUMP CODE," (WV Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)

9. WCAP- I0079-P-A, "NOTRUMP - A NODAL TRANSIENT SMALL BREAK AND GENERAL NETWORK CODE," (iWY Proprietary). (Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)

10. WCAP- 12610, "VANTAGE+ Fuel Assembly Report," (W Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)

11. Letter from V. L. Rooney (USNRC) to J. F. Opeka, "Safety Evaluation for Topical Report, NUSCO-1 52, Addendum 4, 'Physics Methodology for PWR Reload Design,' TAC No. M91815," July 18, 1995.

12. Letter from E. J. Mroczka to the USNRC, "Proposed Changes to Technical Specifications, Cycle 4 Reload Submittal - Boron Dilution Analysis," B13678, December 4, 1990.

13. Letter from D. H. Jaffe (USNRC) to E. J. Mroczka, "Issuance of Amendment (TAC No. 77924)," March 11, 1991.

14. Letter from M. H. Brothers to the USNRC, "Proposed Revision to Technical Specification, Shutdown Margin Requirements and Shutdown Margin Monitor Operability for Modes 3, 4, and 5 (PTSCR 3-16-97), B 16447, May 9, 1997.

15. Letter from J. W. Anderson (USNRC) to M. L. Bowling (NNECO), "Issuance of Amendment - Millstone Nuclear Power Station, Unit No. 3 (TAC No. M98699),"

October 21, 1998.

16. WCAP-8301, "LOCTA-IV Program: Loss-of-Coolant Transient Analysis."

17. WCAP-10054-P-A, Addendum 2, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model."

18. WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thcrmal Overtemperature AT Trip Functions," (Westinghouse Proprietary Class 2).

(Methodology for Specification 2.2.1.)

MILLSTONE - UNIT 3 6-20a Amendment No. x-8,4A7O, 218

v t e Letter Sequence Approval
TAC:MB8387, Relocate TS Parameters to Colr (Approved, Closed)
Initiation Request Acceptance... Administration Questions 21 May 2003 4 September 2003 Answers Results Approval, Approval, Approval Other:
MONTHYEAR2004-03-09 [Table View]

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