ML062140681

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Administrative Correction to Issued Pages in License Amendments
ML062140681
Person / Time
Site: Millstone  Dominion icon.png
Issue date: 08/02/2006
From: Funderburk C
Dominion Nuclear Connecticut
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
06-553
Download: ML062140681 (12)
v • d • e


Text

Dominion Nuclear Connecticut, Inc.

5000 Dominion Boulevard, Glen Allen, Virginla 2 3060 August 2, 2006 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Serial No.:

06-553 NSS&UDF RO Docket Nos:

50-336 50-423 License Nos: DPR-65 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNITS 2 AND 3 ADMINISTRATIVE CORRECTION TO ISSUED PAGES IN LICENSE AMENDMENTS On March 16, 2006 the Nuclear Regulatory Commission issued License Amendment (LA) 291 for Millstone Unit 2 (MPS2) and LA 229 for Millstone Unit 3 (MPS3) to address a variety of administrative changes to the Technical Specifications.

During a review of the issued pages, it was determined that several errors were introduced as a result of processing and software issues.

Dominion Nuclear Connecticut, Inc., requests the NRC to re-issue the affected pages as replacement pages for the associated amendments. A mark-up of the affected pages is contained in to this letter. The replacement pages are contained in Attachment 2.

If you should have any questions regarding this submittal, please contact Mr. Paul R. Willoughby at (804) 273-3572.

Very truly yours, e-C. L. Funderburk Director - Nuclear Licensing and Operations Support Dominion Resources Services, Inc.

for Dominion Nuclear Connecticut, Inc.

Serial No.: 06-553 Docket Nos: 50-336 50-423 Page 2 Commitments made in this letter: None Attachments (2)

CC:

U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1 41 5 Mr. V. Nerses Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North 1 1 555 Rockville Pike Mail Stop 8C2 Rockville, MD 20852-2738 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station Director Bureau of Air Management Monitoring and Radiation Division Department of Environmental Protection 79 Elm Street Hartford, CT 061 06-51 27

Serial No.: 06-553 Docket Nos: 50-336 50-423 ATTACHMENT 1 ADMINISTRATIVE CORRECTION TO ISSUED PAGES IN LICENSE AMENDMENTS MARKED-UP PAGES (3) FOR MPS2 LA 291 AND -

MARKED-UP PAGE (1) FOR MPS3 LA 229 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION, UNITS 2 AND 3

March 16,2006 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 autonlatically removed when THERMAL POWER is 2 5% of RATED THERMAL POWER.

(b) Trip may be lna11ualIy bypassed when steam generator pressure is < 800 psia and all CEAs are f~dly inserted; bypass shall be automatically removed when steam generator pressure is 2 800 psia.

(c) Trip may be bypassed below 15% of RATED THERMAL POWER; bypass shall be at~tomatically ~emoved \\vlien THERMAL POWER is 2 15?4 ol'RATPD TI-IERMAL POWER.

(d) Trip does not need ro be OPERABLE irall the conirol rod drive meclmisms are de-energized 1

or if the RCS boron concentra[ion is greater than or equal to the ref~~eling con cent^-ation of Specification 3.9.1.

(e) DELETED (0 AT Powel-input lo (rip m y be bypassed below 5% of RATED THERMAL POWER; bypass shall be au~oma[ically sen~oved when THERMAL POWER is 2 5% oCIlATED THERMAL POWER.

ACTION STATEMENTS ACTION 1 - With h e nuntber ol'cltannels OPERABLE one less tltall ~equired by the Mit~itnun~

Channels OPERABLE requil.ement, restore the inoperable channel to OPERABLE status within 48 ltours or be in HOT STANDBY within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and/or open the protective system trip breakess.

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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The inoperable charnel shall either be restored to f i OPERABLE status, or pIaced in the tripped condition, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 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.

The Minimrm Channels OPERABLE requirement is met; however, one additional channel may be removed from service for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, provided one of the inoperable channels is placed in the tripped condition.

MILLSTONE - UNIT 2 314 3-4 Amendment No. 4,38,72,MB, 439, 225, £24,288,291

March 16,2006 REACTOR COOLANT SYSTEM COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION LIMITING CONDITION FOR OPERATlON ri.

/ 3.4fl ) Two reactor coolant loops shall be OPERABLE and in operation.

%~CABILITY MODES 1 and 2.

I ACTION:

With the requil.ements of the above specification not met, be in at lensr NOT STANDBY within G hours.

SURVEILLANCE REQUIREMENTS 4.4 I. 1 Thc above requrrccl reactor coolant loops shall be verified to be in operation at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

MILLSTONE - UNIT 2 I

314 4-1 Amendment No. 58,459, W, 249,291

March 16,2006 PLANT SYSTEMS MAIN FEEDWATER ISOLATION COMPONENTS (MFICs)

LIMITING CONDITION FOR OPERATION (Continued)

With two or more of the feedwater isolation components inoperable in the same flow path, either:

1.

Restore the inoperable co~npoi~ent(s) to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> until ACTION 'a' applies, or I

2.

Isolate the affected flow path within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and verify that the inoperable feedwater isolation components are closed or isolatedfsecured once per 7 clays, or-

3.

Be in HOT SI-IUTDOWN within the next I2 hours SURVEILLANCE REQUIREMENTS 4.7.1.6 Each feedwater isolation vnlvelfeedwlater pump trip circuitry shall be demonstrated OPERABLE at Irast oncc pel-18 ~nonths by:

a.

VrriSyillg that on '.4' main steam isola1ion lest signal. each isolation wlve actuates to ils isolation position. and

c.

Verifying that 011 'A' 11iein skain isolation test signal, each Seerlwaler pump trip circuit actuates, and

d.

Verifying thal on 'B' main steam isolation test signal, each feedwater pump trip circuit acluates.

MILLSTONE - UNIT 2 A~neiid~nent No. W, 2 9 1

March 16, 2006 WACTIVITY CONTROL SYSTEMS CONTROL ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION

3. I.3.6 The control banks shall be limited in physical insertion as specified in the CORE OPERATING LIMITS WPORT (COLR).

I APPLICABILITY MODES 1

  • and 2" **.

ACTION:

With the control banks inserted beyond the insertion limits specified in the COLR, except for surveillance testing pursuant to Specification 4.1.3.1.2:

a.

Restore the control banks to within the limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or

b.

Reduce THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the bank position using the insertion limits specified in the COLR, o n

c.

Be in at least HOT STANDBY SURVEILLANCE REQUIREMENTS u 4.1.3.6 The position of each control bank shall be determined to be within the insertion limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the rod insertion limit monitor is inoperable, then verify the individual rod positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

  • See Special Test Exceptions Specifications 3.10.2 and 3.10.3.
    • With Kefi greater than or equal to 1.

MILLSTONE - UNIT 3 3/4 1-27 Amendment No. 58,439,229

Serial No.: 06-553 Docket Nos: 50-336 50-423 ATTACHMENT 2 ADMINISTRATIVE CORRECTION TO ISSUED PAGES IN LICENSE AMENDMENTS CORRECTED PAGES (3) FOR RE-ISSUE FOR MPS2 LA 291 AND -

CORRECTED PAGE (1) FOR RE-ISSUE FOR MPS3 LA 229 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION, UNITS 2 AND 3

March 16,2006 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 2 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 2 800 psia.

(c) Trip may be bypassed below 15% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is Z 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 2 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 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> andlor open the protective system trip breakers.

ACTION 2 - With the number of OPERAE3LE 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The inoperable channel shall either be restored to OPERABLE status, or placed in the tripped condition, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

b.

Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, all functional units receiving an input from the inoperable channel are also declared inoperable, and the appropriate actions are taken for the affected fhctional units.

c.

The Minimum Channels OPERABLE requirement is met; however, one additional channel may be removed from service for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, provided one of the inoperable channels is placed in the tripped condition.

MILLSTONE - UNIT 2 314 3-4 Amendment No. 9,38,72,+4-6,439, 225,224,288,29 1

REACTOR COOLANT SYSTEM COOLANT LOOPS AND COOLANT CIRCULATION March 16,2006 STARTUP AND POWER OPERATION LIMITING CONDITION FOR OPERATION 3.4.1.1 Two reactor coolant loops shall be OPERABLE and in operation.

APPLICABILITY MODES 1 and 2.

ACTION:

With the requirements of the above specification not met, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.1.1 The above required reactor coolant loops shall be verified to be in operation at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

MILLSTONE - UNIT 2 Amendment No. 58, 69, 230, W, Z 9 1

PLANT SYSTEMS MAIN FEEDWATER ISOLATION COMPONENTS {MFICs)

March 16,2006 LIMITING CONDITION FOR OPERATION (Continued)

b.

With two or more of the feedwater isolation components inoperable in the same flow path, either:

1.

Restore the inoperable component(s) to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> until ACTION 'a' applies, or

2.

Isolate the affected flow path within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and verify that the inoperable feedwater isolation components are closed or isolatedfsecured once per 7 days, or

3.

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

SURVEILLANCE REQUIREMENTS 4.7.1.6 Each feedwater isolation valvelfeedwater pump trip circuitry shall be demonstrated OPERABLE at least once per 18 months by:

a.

Verifying that on 'A' main steam isolation test signal, each isolation valve actuates to its isolation position, and

b.

Veriving that on 'B' main steam isolation test signal, each isolation valve actuates to its isolation position, and

c.

Verifjring that on 'A' main steam isolation test signal, each feedwater pump trip circuit actuates, and

d.

Verifying that on 'B' main steam isolation test signal, each feedwater pump trip circuit actuates.

MILLSTONE - UNIT 2 Amendment No. %,29 1

REACTIVITY CONTROL SYSTEMS CONTROL ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6 The control banks shall be limited in physical insertion as specified in the CORE OPERATING LIMITS REPORT (COLR).

I APPLICABILITY MODES 1

  • and 2* **

ACTION:

With the control banks inserted beyond the insertion limits specified in the COLR, except for surveillance testing pursuant to Specification 4.1.3.1.2:

a.

Restore the control banks to within the limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or

b.

Reduce THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the bank position using the insertion limits specified in the COLR, or

c.

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

SURVEILLANCE REQUIREMENTS 4.1.3.6 The position of each control bank shall be determined to be within the insertion limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the rod insertion limit monitor is inoperable, then verifjr the individual rod positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

  • See Special Test Exceptions Specifications 3.10.2 and 3.10.3.
  • With Keff greater than or equal to 1.

MILLSTONE - W I T 3 Amendment No. 50,433,229

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