ML20092H640

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Amend 153 to License DPR-65,changing TS Index & Sections 3.1.3.6,3.9.18,3.9.20, & Bases Sections 3/4.9.17,3/4.9.18, 3/4.9.19 & 3/4.9.20 to Correct Various Editorial & Typos
ML20092H640
Person / Time
Site: Millstone 
Issue date: 02/14/1992
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Northeast Nuclear Energy Co (NNECO), Connecticut Light & Power Co, Western Massachusetts Electric Co
Shared Package
ML20092H642 List:
References
DPR-65-A-153 NUDOCS 9202210233
Download: ML20092H640 (22)
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- UNITED STATES

- NUCLEAR REGULATORY COMMISSION g

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' WASHINGTON, D, C. 20555 -

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NORTHEAST NUCLEAR ENERGY COMPANY 1

THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 HILLSTONE NUCLEAR POWER STAT'ON. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE

-Amendment No. 153 License No. 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 October _ 9,1991, as supplemented by letter.of November 26, 1991, 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; B.-

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 l-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; E

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

9202210233 920214 PDR ADOCK 05000336 P

PDR

__,._,,... - _ _... _. _ _. a _

- 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. DPR-65 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.153, 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 40 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 0/j /

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Joh

. Stolz, Director Pr ject Directorate 1-4

[DvisionofReactorProjects-I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 14, 1992 i

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A

ATTACHMENT TO LICENSE AMENDMENT NO. 153 FACILITY OPERATING LICENSE NO. OPR-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 II II IV IV VI VI VII VII IX IX X

X XII XII XIV XIV XVI.

XVI XVIII XVIII 3/4 I-28 3/4 I-28 3/4 I-29 3/4 I-29 3/4 4-23 3/4 4-23 3/4 9-22 3/4 9-22 3/4 9 3/4 9 3/4 9-27 3/4 9-27 B 3/4 9-3 B 3/4 9-3 8 3/4 9-4 8 3/4 9-4 B 2-7 8 2-7

s._#

INDEX DEFINITIONS EME SECTION Enclosure Building Integrity................................

1-5 Reactor Trip System Response Time...........................

1-5 Engineered Safety Feature Response Time.....................

1-5 Physics Tests...............................................

1-6 Unrodded Integrated Radial Peaking Factor - F..............

1-6 r

Source Check................................................~

1-6 Radiological Effluent Monitoring and Offsite Dose Cal cul ation Manual (REM 0DCM)..............................

1-6 Radioactive Waste Treatment Systems......................

1-6 Purge - Purging..............................................

1-6 Venting.....................................................

1-8 Member (s) of the Public.....................................

18 Site Boundary...............................................

1-8 Unrestricted Area...........................................

1-8 Storage Pattern.............................................

1-8 l

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MILLSTONE - UNIT 2 II Amendment No. 7Ef, JJJ, JJ7, 0830 JJJ 153 1

- 1 l

f INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE00iREMENTS SECTION EAE A

'3/4.0'-APPLICABillTY........................................

3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS E-3/4.1.1 BORAT10N CONTROL.................................

3/4 1-l' Shutdown Margin - T avg 200*F....................

3/4 1 Shutdown Margin - Tavg 200'F....................

3/4 1-3 Boron Di1ution'..................................

3/4 1-4 Moderator Temperature Coefficient (MTC).........

3/4 1-5 Minimum Temperature for Cri ticality.............

3/4 1-7

-3/4.1.2 BORAT10N SYSTEMS................................

3/4 1-8 Flow Paths'- Shutdown...........................

3/4 1 8 Flow Paths - Operating..........................

3/4 1-9

-l Charging Pump - Shutdown........................

3/4 1-12 9

. Charging Pumps - Operating-......................

3/41-13 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 3/4;1.3 MOVABLE CONTROL ASSEMBLIES......................

3/4 1 '

Full Length CEA Group Position..................

3/4 1-20 Position Indicator Channels.....................

3/4 1-24 CEA Drop Time....................................

3/4 1 Shutdown CEA Insertion ~ Limit....................

3/4 1-27 e

i Regulating CEA Insertion Limits.................

3/4 1-28 Control Rod Drive Mechani sms....................

3/4 1-31 MILLSTONE - UNIT 2 IV Amendment No. JE, Jpf, JJE 153 0031 t.

.__.s._

h h4' INDEX I

LIMITING CONDITIONS FOR-OPERATION AND SURVEILLANCE RE0VIREMENTS I

SECTION P_AqE

{

A 3/4.4.2 SAFETY VALVES..................................

3/4 4-2 3.4.4.3 RELIEF-VALVES..................................

3/4 4-3 3/4.4.44 PRESSURIZER....................................

3/4 4-4 3/4.4.5 STEAM GENERATORS...............................

3/4 4-5 3/4.4.6 -

REACTOR COOLANT SYSTEM LEAKAGE.................

3/4.4 8 Leakage Detection Systems......................

3/4 4-8 Reactor Coolant System Leakage.................

3/44-_9 3/4.4.7 CHEMISTRY ~......................................-

3/4 4 10 3/4.4.8 SPECIFIC ACTIVITY..............................

3/4 4-13

-3/4.4.9 PRESSURE / TEMPERATURE LIMITS....................

3/4 4-17 Reactor Cool ant System.........................

3/4-4 17

Pressurizer....................................

3/4 4-21 Overpressure Protection Systems................-

3/4 4-21a 3/4.4=10-

-STRUCTURAL INTEGRITY...........................

3/4.4-22 3/4.4.11-FEACTOR COOLANT SYSTEM VENTS...................

3/4 4-23 3/4.5 EMERGENCY CORE COOLING a STEMS (ECCS) 3/4.5.1

SAFETY INJECTION TANKS........................

3/4 5-1

.3/4.5.2-ECCS SUBSYSTEMS - T vg 2 300*F.................

3/4 5 '

a 3/4.5.3 ECCS' SUBSYSTEMS - Tavg <300'F-..................

7/5 <7 3/4_5.4 REFUELIN'i WATER STORAGE TANKL...................

3/4 5-8

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MILLSTONE - UNIT 2 VI Amendment No. JS, 72, J#p 153 0032-

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INDEK llMITING CONDITIONS FOR OPERATION AND SURVElllANCE RE0VIREMENTS SECTION PJ.GE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT...............................

3/4 6-1 Containment In+egrity.............................

3/4 6-1 Containment Leakage...............................

3/4 6-2 Containment Air Locks.............................

3/4 6-6 I n t e rn al Pre s s u re.................................

3/4 6-B Air Temperature...................................

3/4 6-9 Containment Structural Integrity..................

3/4 6-10 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS..............

3/4 6-12 Containment Spray System..........................

3/4 6-12 Containment Air Recirculation System..............

3/4 6-14 3/4.6.3 CONTAINMENT ISOLATION VALVES......................

3/4 6-15 Containment Ventilation System....................

3/4 6-19 3/4.6.4 COMBUSTIBLE GAS CONTROL...........................

3/4 6-20 Hydrogen Monitors.................................

3/4 6-20 Electric Hydrogen Recombiners = W.................

3/4 6-21 Hydrogen Purge System.............................

3/4 6-23 Post-Incident Recirculation Systems...............

3/4 6-24 3/4.6.5 SECONDARY CONTAINMENT.............................

3/4 6-25 Enclosure Building Filtration System..............

3/4 6-25 Enclosure Building Integrity......................

3/4 6 L 1

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MILLSTONE - UNIT 2 VII Amendment No. JpA 153 0033 O

INDEX llMITING CONDITIONS FOR OPERATION AND SURVElllANCE REQUIREMENTS SECTION 1201 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 3/1 9.4 CONTAINMENT PENETRATIONS.........................

3/4 9 4 2

3/4.9.5 COMMUNICATIONS...................................

3/4 9-5 3/4.9.6 CRANE OPERABILITY - CONTAINMENT. BUILDING.........

3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING...

3/4 9-7 3/4.9,8 SHUTDOWN COOLING AND COOLANT CIRCULATION.........

3/498 3/4.9.9 CONTAINMENT AND RADIATION MONITORING.............

3/4 9-9 3/4.9.10 CONTAINMENT PURGE VALVE ISOLATION SYSTEM.........

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 STORAGE POOL RADIATION MONITORING................

3/4 9-13 3/4.9.14 STORAGE POOL AREA VENTILATION SYSTEM -

FUEL MOVEMENT....................................

3/4 9-14 3/4.9.15 STORAGE POOL AREA VENTILATION SYSTEM -

FUEL STORAGE.....................................

3/4 9-16 3/4.9.16 SHIELDED CASK....................................

3/4 9 3/4.9.17 MOVEMENT OF FUEL OVER REGION II RACKS............

3/4 9-21 3/4.9.18 SPENT FUEL POOL - REACTIVITY CONDITION...........

3/4 9-22 3/4.9.19 SPENT FUEL. POOL - STORAGE PATTERN,...............,

3/4 9-26 3/4.9.20 SPENT FUEL P0OL - CONSOLIDATION..................

3/4 9-27 L

3/4.10 SPECIAL TEST EXCEPTIONS 1'

3/4.10.1 SHi tTDOWN MARG I N..................................

3/4 10-1 3/4.10.2 GROUP HEIGHT AND INSERTION LIMITS................

3/4 10-2 3/4.10.3 PRESSURE / TEMPERATURE LIMITATION - REACTOR CRITICALITY......................................

3/4 10-3 MILLSTONE - UNIT 2 IX Amendment No. O, JE/, JA9, JJ7 153 0034

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION P_Al[

A 3/4.10.4 PHYSICS TESTS...................................

3/4 10-4 3/4.10.5 CENTER CEA MISALIGNMENT.........................

3/4 10 5 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS................................

3/4 11-1 CONCENTRATION...................................

3/4 11-1 DOSE, LIQUIDS...................................

3/4 11-2 3/4.11,2 GASEOUS EFFLUENTS...............................

3/4 11-3 DORE RATE.......................................

3/4 11-3 DOSE, N0BLE GASES...............................

3/4 11-4 DOSE, RAD 1010 DINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES................................

3/4 11-5 3/4.11.3 TOTAL DOSE.....................................

3/4 11-6 l

l MILLSTONE - UNIT 2 X

Amendment No. JJf, JJJ 153 0035 i

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INDEX BASES-SECTION-11EE 3/4.4-REACTOR _ COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION.............

B3/44-1 3/4.4.2 SAFETY VALVES.....................................

B 3/4 4 1 3/4;4.3 RELIEF VALVES:.....................................

B 3/4 4 2 13/4.4.4 PRESSURIZER.......................................

B 3/4 4-2

-3/4.4.5

-STEAM GENERATORS..................................

B 3/4 4-2 3/4.4.6 REACTOR C00LANTESYSTEM LEAKAGE....................

B 3/4 4 3 3/4.4,7:

CH EM I S T RY :.........................................

B 3/4 4-4 3/4.4.8.

SPECIFIC _ ACTIVITY.................................

B 3/4 4-4

-3/4.4.9

PRESSURE / TEMPERATURE LIMITS.......................

B 3/4 4-5 3/4.4.10. STRUCTURAL-INTEGRITY..............................

B 3/4 4-11 L3/4.4.11 REACTOR COOLANT-SYSTEM VENTS......................

B 3/4 4-8 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.l_

SAFETY INJECTION TANKS............................

B 3/4 5-1

-3/4.5.2-and 3/4.5.3-ECCS SUBSYSTEMS........................

B 3/4 5-1 3/4.5.4 REFUELING WATER' STORAGE TANK (RWST),,.............

B 3/4-5-2

~- 3/4 ~. 6 CONTAINMENT-SYSTEMS

=3/4.6.1 PRIMARY' CONTAINMENT...............................

B 3/4 6 3/4.6.2 -DEPRESSURIZATION AND COOLING SYSTEMS..............

B 3/4 6-3 3/4.6.3 _ CONTAINMENT ISOLATION-VALVES......................

B 3/4-6-3'

-3/4.6.4 COM8USTIBLE GAS-CONTROL...........................

B 3/4 6-4 3/4.6.5' SECONDARY CONTAINMENT.............................

B 3/4 6-5 MILLSTONE - UNIT 2 XII' Amendment No. JJ, JJ, 72, JJJ 153 0036

INDEX BASES SECTION EAGE 3/4.9.9 and 3/4.9.10 CONTAINMENT AND RADIATION MONITORING AND CONTAINMENT PURGE VALVE ISOLATION SYSTEM.................

B 3/4 9-2 3/4.9.11 and 3/4.9.12 WATER LEVEL - REACTOR VESSEL AND STORAGE P0OL WATER LEVEL.................................

B 3/4 9-2 3/4.9.13 STORAGE POOL RADIATION MONITORING...................

B 3/4 9 3 3/4.9.14 and 3/4.9.15 STORAGE POOL AREA VENTILATION SYSTEM...

B 3/4 9-3 3/4.9.16 SHIELDED CASK.......................................

B 3/4 9-3 3/4.9.17 MOVEMENT OF FUEL OVER REGION 11 RACKS...............

B 3/4 9-3 3/4.9.1B SPENT FUEL P0OL - REACTIVITY CONDITION..............

B 3/4 9-3 3/4.9.19 SPENT FUEL P0OL - 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 PRESSURE / TEMPERATURE LlHITATION -

REACTOR CRITICALITY...............................

B 3/4 10-1 3/4.10.4 PHYSICS TESTS.......................................

B 3/4 10-1 3/4.10.5 CENTER CEA MISALIGNMENT.............................

B 3/4/10-1 J/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS....................................

B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS...................................

B 3/4 11-2 3/4.11.3 70TAL DOSE..........................................

B 3/4 11-4 MILLSTONE - UNIT 2 XIV Amendment No. ES, /pf, J /, JJ7 153 0037

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INDEX i

ADMINISTRATIVE CONTROLS

=SECTION pag A

a 6.- l RESPONSIBILITY..........................................

61 b

6.2 ORGANIZATION...........................................

6-1 Offsite and Onsite Organizations.....................

6-1 Facility Staff......=.................................

6-1

-i 6.3 UNIT STAFF 00ALIFICATIONS..............................

6-la-6.4 TRAINING......'.........................................

6-5 6.5 REVIEW AND AUDIT 6.5.1 ' PLANT OPERATIONS REVIEW COMMITTEE (PORC)

"~

' Function............................................,

6-5

' Composition..........................................

'6-5 Alternates...........................................

6-5 Meeting Frequency....................................

6-6 Quorum...............................................

6-6 Responsibilities.....................................

6-6 Authority............................................ 7 Records..............................................

6-7 6.5.2 SITE OPERATIONS REVIEW COMMITTEE (SORC)

Function.............................................

6-7 Composition-.................................,........

6-7 Alternates...........................................

6-8

-Meeting Frequency....................................

6-8 Quorum...............................................

6-8 Responsibilities.....................................

6-8

-Authority _............................................

6-9 Records..............................................

6-9 MILLSTONE - UNIT 2 XVI Amendment No. J#f, Igg 153 0038

o 11 3:

INDEX ADMINISTRATIVE CONTROLS SECTION-EAQ1 6.9 REPORTING RE0VIREMENTS f:'

. 6.9.1. ROUTINE REPORTS.......................................

6-17 STARTUP REP 0RTS........................................

6 17 ANNUAL REP 0RTS.........................................

6-18

. MONTHLY OPERATING REP 0RT'..............................

6-19 CORE OPERATING LIMITS REPORT..........................

6-19 6.9.2 -SPECIALLREPORTS.......................................

6-19

'6.10' RECORD RETENT[QH........................................

6-20 6.11 RADIATION PROTECTION PROGRAM..........................

6-21 6.12 'HIGH RADIATION AREA....................................

6 21 d

6~13' SYSTEMS INTEGRITY......................................

6-22

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=6.14 IODINE MONITORING......................................

6-22 6-.15 RADIOLOGICAL' EFFLUENT-MONITORING AND OFFSITE DOSE' CALCULATION MANUAL (REMODCM) 6-23

6.16: RADI0 ACTIVE = WASTE TREATHEMI............................

6-23 6.17 SECONDARY WATER CHEMISTRY...............................

6-24 6.18 PASS / SAMPLING'AND ANALYSIS OF PLANT EFFLUENTS..........

6-24 MILLSTONE _- U' NIT:2 XVIII Amendment No. JJ, JJ, %), %%, JJJ

'8818 J#f,' JJJ, Jf% 153 i

.d

' REACTIVITY CONTROL SYSTEMS REGULATING CEA INSERTION tlMITS-LIMITING CONDITION FOR OPERATION 3.1.3.6 The regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits provided in the CORE OPERATING LlHITS 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 restricted to the limits provided in the CORE OPERATING LIMITS REPORT.

APPLICABILITY: MODES 1* and 2*#.

ACIl03:

a.

With the regulating CEA groups inserted beyond the Transient Insertion Limits provided in the CORE OPERATING LIMITS REPORT, 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, 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

> 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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:

1. -

The Short Term Steady State Insertion Limits specified in the CORE OPERATING LIMITS REPORT are not exceeded, or 2.

Any subsequent increase in THERMAL POWER is restricted to 1 5% of RATED THERMAL POWER per hour.

  • See Special Test Exception 3.10.2 and 3.10.5.
  1. With K,ff 1 1.0.

MILLSTONE-UNIT 2 3/4 1-28 Amendment No. JfE 153 0040

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' REACTIVITY CONTROL SYSTEMS REGULATING CEA INSERTION LIMITS (Continued)

LIMITING CONDITION FOR OPERATION-With:the regulating CEA groups inserted between the Long Term Steady c.

State 1 Insertion Limits and the Transient Insertion Limits-specified in the CORE OPERATING LIMITS-REPORT for intervals >-5 EFP9-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 provided in the CORE OPERATING LIMITS REPORT within two hours, or 2.

~Be in HOT STANDBY within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE RE0VIREMENTS

~

4.1.3.6 The position of each regulating CEA group shall be determined to be within the Transient-Insertion Limits provided in the CORE OPERATING LIMITS

REPORT _ 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 PDIL Auctioneer Alarm Circuit is. inoperable, then verify the individual CEA 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 />.1-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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> specified.

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-MILLSTONE - UNIT 2 3/4 1-29 Amendment No. JfE 153 0041 l'

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REACTOR-COOLANT SYSTEM REACTOR COOLANT-SYSTEM VENTS-LIMITING CONDITION FOR OPERATION 3.4.11-At least-one reactor coolant-system vent path consisting of at least-two valves in series capable of being powered from emergency buses shall be OPERABLE and' closed at each of the following locations:

a.

Reactor Vessel head b.

Pressurizer steam space APPLICABILITY: -MODES 1, 2, 3, and 4.

-ACTION:

a.

With the Pressurizer vent path inoperable STARTUP and/or POWER OPERATION may continue provided that 1) the ~ inoperable vent path is maintained closed with -power removed from - the valve actuator of all.the valves ' in the ' inoperable vent path and

11) nne' power operated relief valve (PORV) and-its : associated -

Lblo.k valve-is OPERABLE; otherwise, restore either the boperable vent path or one PORV and its associated block valve to OPERABLE status within 30 days, -or submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10; days outlining the cause of the malfunction and the plans.for restoring the path to OPERABLE status, b.

With the Reactor Vessel Head vent path inoperable, STARTUP and/or POWER: OPERATION may continue: provided that'.the inoperable vent path is maintained. closed with power removed from the valve' actuator of all the valves in the inoperable vent path;- restore the Reactor Vessel -Head vent path to OPERABLE status within 30 days or submit a Special Report to the Commission-pursuant to Specification 6.9.2 within the next 10 days outlining the cause of-the malfunction and the plans for restoring the path to OPERABLE status.

SURVEILLANCE-RE0VIREMENTS-l

' 4. 4.11 -

Each reactor coolant system vent path _ shall be demonstrated OPERABLE at least once per 18 months by:

1.:

Verifying all manual isolation -valves in each vent path are locked in the open position.

2.

Cycling each - valve in the vent path through at least once complete cycle of full travel from the control room during COLD l

SHUTDOWN or REFUELING.

3.

Verifying flow through the reactor coolant vent system vent paths during venting during COLD-SHUTDOWN or REFUELING.

1 L

MILLSTONE - UNIT 2 3/4 4-23 Amendment No. /$, 72, JJ#,

~

JEJ 153

REFUELING OPERATIONS SPENT FUEL POOL - REACTIVITY CONDITION LIMITING CONDITION FOR OPERATION 3.9.18 The Reactivity Con ition of the spent fuel pool shall be such that K*fg is less than or equal to 0.95 at all times.

APPLICABILITY: Whenever-fuel is in the spent fuel pool.

ACTION:

Borate until a K,7f f.95 is reached.

SURVEILLANCE REOUIREMENT 4.9.18.1-Ensure'that all fuel assemblies to-be placed in Region II (as shown in Figure 3.9-2) of the-spent fuel pool are within the enrichment and burn-up limits of Figure 3.9.1 by checking the assembly's design and burn-up documen-tation.

4.9.18.2 Ensure that the contents of each consolidated fuel storage box to'be placed in Region II (as shown in Figure 3.9-2) of the spent fuel pool are-within?the enrichment and burn-up limits of Figure 3.9-3 by checking the design and burn-up documentation for storage box contents.

MILLSTONE UNIT 2 3/4 9-22 Amendment No. JES, JJ7 153 0043

REFUELING OPERATIQRS SPENT FUEL POOL - STORAGE PATTERN

LIMITING CONDITION FOR OPERATION 3.9.19 Each: STORAGE PATTERN of the Region-Il spent fuel - pool racks shall require either that:-

.(1) A cell blocking device is installed in those cell locations shown in Figure 3.9-2; or (2)- If a cell blocking device has been removed,-all cells of the STORAGE P;TTERN must have consolidated fuel in them, including the formerly blocked location; or

_(3), Meet both (a) and (b):

(a). If a cell blocking device has been removed, all cells of the STORAGE PATTERN must have consolidated fuel in them except the

-_formerly blocked location.

(b) The formerly blocked location is vacant and a consolidated fuel box or cell blocking device is -immediately being placed into theLformerly blocked cell.

APPLICABILITY:

Fuel in the Spent Fuel Pool ACTION:-

Take immediate action to comply with either 3.9.19(1),-(2), or (3).

SURVEILLANCE REOUIREMENTS

4.9.19. Verify that 3.9.19 is atisfied ~at the following times.

(1) ' Prior to removing a cell blocking device (2)

Prior to removing a_ consolidated fuel storage box from its Region 11 storage location.

i E

MILLSTONE - UNIT 2 3/4 9-26 Amendment No. JJ7 153 0G44

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REFUELING OPERATIQld SPENT FUEL POOL - CONSOL10AT10ff llMITING CONDITION FOR OPERATION 3.9.20 Prior to consolidation of spent fuel assemblies, the candidate fuel assemblies must have decayed for at least 5 years.

APPLICABillTY:

During all consolidation operations.

LC11D!l:

With the requirements of the above specification not satisfied, replace candidate assembly with an appropriate substitute or suspend all consolidation activities.

SVRV[lll AfiCE _ RLQtjlREMENTS 4.9.20 The decay time of all candidate fuel as.cmblics for consolidation shall be determined to be greater than c-

qual to five years within l

7 days prior to moving the fuel assi..:lty tote the consolidation work station.

MILLSTONE - UNIT 2 3/4 9-27 Amendment No. JJ/, JJE 153 0045

REFUELING OPERATIQtfA BASES j

3/4.9.13 STORAGE POOL RADIATION MONITORING The OPERABILITY of the sturage

>ool radiation monitors ensures that sufficient radiation monitoring capability is available to detect excessive radiation levels resulting from 1) the inadvertent lowering of the storage pool water level or 2) the release of activity from an irradiated fuel atsembly.

3/4.9.14 &,}// ^ '5 STORAGE POOL AREA VENillATION SYSTEM l

The limi.a,os on the storage pool area ventilation system ensures that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcori adsorber prior to discharge to the atmosphere.

The OPERABILITY of _ this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.

3/_4.9.16 SHl(LQ10 CASK The limitations of this specification ensure that in an event of a cask tilt accident 1) the doses from ruptured fuel assemblies will be within the assumptions of the safety analyses, 2) K,77 will remain s.95.

3/4.9.17 MOVEMENT OF FUEL 0VER RIG 10N II RACKS The limitations of this specification ensure that, in the event of a fuel assembly or a consolidated fuel storage box drop accident into a Region !!

rack location completing a 4-out of 4 fuel assembly geometry, K,77 wH1 remain i

5 0.95.

I 3/4.9.18 SPENT FUEL POOL - REACTIVITY CONDIT10fi The limitations described by figure 3.91 ensure that the reactivity of fuel assemblies and consolidated fuel storage boxes, introduced into the Region !! spent fuel racks, are conservathely within the assumptions of the safety analysis, i

MILLSTONr. UNIT 2 B 3/4 9 3 Amendment No. JS, JEJ, JJ7 153 0066 IL

REFMEllNG OPERATIONS BASES 3/4.9.19 SPENT FUEL POOL - STORAGE PATTERN The limitations of this specification ensure that the reactivity conditions of the Region !! storage racks and spent fuel pool K,77 will remain less than or equal to 0.95.

The Cell Blocking Devices in the 4th location of the Region !! storage racks are designed to prevent inadvertent placement and/or storage of fuel assemblies in the blocked locations.

The blocked location remains empty to provide the flux trap to maintain reactivity control for fuel assembly storage in any adjacent locations.

Only loaded consolidated fuel storage boxes may be placed and/or stored in the 4th location, completing the STORAGE PATTERN.

after All

adjacent, and
diagonal, locations are occupied by loaded consolidated fuel storage boxes.

3/4.9.20. SPENT FUEL P0OL CONSOL10ATI.QN The limitations of these specifications 3.nsure that the decay heat rates and radioactive inventory of the candidate fuel assemblies for consolidation are conservatively within the assumptions of the safety analysis.

MILLSTONE - UNIT 2 B 3/4 9-4 Amendment No, JJJ 153 0047 i

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LIMITING SAFETY SYSTEM SETTINM BASES Thermal Marain/ Low Pressure (Continued) i The trip is initiated whenever the reactor coolant system pressure signal l

dross below either 1850 psia or a computed value as described below, whichever is 11gher. The computed value is a function of.the higher of AT power or neutron power, reactor inlet temperature, the number of reactor coolant pumps operating and the AXIAL SHAPE INDEX. The minimum value of reactor coolant l

flow ratei the maximum AZIMUTHAL POWER TILT and the maximum CEA deviation permitted for continuous operation are assumed in the generation of this trip function.

In addition, CEA group sequencing in accordance with Specifications i

3.1.3.5 and 3.1.3.6 is assumed.

Finally, the maximum insertion of CEA banks t

-which can occur during any anticipated operational occurrence prior to a Power

~

Level High trip is assumed.

t i

Thermal Margin / Low Pressure trip setpoints are derived from the core safety limits -through application of appropriate allowances for equipment response time measurement uncertainties and processing error. A safety margin is provided which includes:

an allowance of 5% of RATED THERMAL POWER to compensate for potential. power measurement error; an allowance of 2*f to i

compensate for pntential temperature h4asurement uncertainty; and a further allowance of 74 psi to compensate for pressure measurement error, trip system processing. error, and time delay associated with providing effective termina-tion of-the occurrence that exhibits the most rapid decrease in margin to_ the safety limit. The 74 psi allowance is made up of a 5 psi bias, a 19 psi pressure measurement allowance and a 50_ psi time delay allowance.

Loss of Turbine A Loss of Turbine trip causes a direct reactor trip when operating above 15% of RATED THERMAL POWER. 'This trip-provides turbine protection, reduces the severity of the ensuring transient and helps avoid t1e lifting of the main steam line safety valves durin service life of these values. g the ensuing transient,- thus extending the

-No credit was'taken in the accident analyses for operation of this tri n its functional capability at the specified trip setting is required to en1ance the overall reliability of the Reactor Protec-tion System.

2 MILLSTONE - UNIT 2 B 2-7 Amendment No. 75, JJ, JJJ 153 0048

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