ML20155F985

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Proposed Tech Specs Re Editorial Changes & Typographical Corrections
ML20155F985
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 10/30/1998
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20155F963 List:
References
NUDOCS 9811060171
Download: ML20155F985 (30)
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Text

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!, - U. S. Nucirr Regulatory Commission CY-98-199/ Attachment 1/Page 2 PAGE SECTION EXPLANATION OF DIFFERENCE XI 3/4.9 Entry for 3/4.9.16 SPENT FUEL POOL COOLING - DEFUELED, and page number 3/4 9-21 missing.

XIll 3/4.3.3.7 INSTRUMENRATION should be INSTRUMENTATION.

XIll 3/4.3.3.8 INSTRUMENTION should be INSTRUMENTATION. I XIV 3/4.7.1 The blank line after 3/4.7.1 should be deleted.

XV Bases 3/4.9 Entry for 3/4.9.16 SPENT FUEL POOL COOLING - DEFUELED, l and page number B3/4 9-5 missing. )

XV 3/4.11.2.3 NOBEL CASES should be NOBLE GASES.

l l XIX 6.9.1 Should show three DELETED under Routine Reports.

3/4 3-44 3.3.3.7 In the footnote "purposse" should be " purpose" and "requwed" i should be " required".

l l 3/4 11-5 3.11.2.3 The word "from" should be between "PUBLIC" and " tritium" in the LCO statement.

B3/4 3-1 B3/4.3 Should say " BASES 3/4.3.1 THROUGH 3/4.3.2".

1 B3/4 3-2 BASES 3.3.3 Should show sections 3/4.3.3.1, 3/4.3.3.2 , 3/4.3.3.5 and  !

3/4.3.3.6 as DELETED.

B3/4 3-3 BASES 3.3.3 Should show sections 3/4.3.3.9 and 3/4.3.4 as DELETED. I l

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'l 9811060171 981030 "

ADOM 0500 2 3 hDR October 1998

Jun2 30, 1998

, 6 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

-SECTION* pgg 3/4.9 REFUELIN(LOPERATIONS 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 FIGURE 3.9 1 REQUIRED REACTOR HOLD TIME FOR A FULL CORE OFFL0AD............................................... 3/4 9 3a 3/4.9.4 CONTAINMENT. BUILDING PENETRATIONS...................... 3/4 9 4 3/4.9.5 COMMUNICATIONS......................................... 3/4 9 5 3/4.9.6 MANIPULATOR CRANE...................................... 3/4 9 6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING ............ 3/4 9 7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL....................................... 3/4 9 8 LOW WATER LEVEL........................................ 3/4 9 9 3/4.9.9 CONTAINMENT PURGE SUPPLY, PURGE EXHAUST AND PURGE EXHAUST BYPASS ISOLATION SYSTEM................. 3/4 9 10 3/4 9.10 . WATER LEVEL REACTOR VESSEL. . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9 11 3/4.9.11 WATER LEVEL STORAGE P00L.............................. 3/4 9 12 3/4.9.12 FUEL STORAGE BUILDING AIR CLEANUP SYSTEM.............. 3/4 9 13 3/4.9.13 MOVEMENT OF FUEL.IN SPENT FUEL P00L................... 3/4 9-15 3/4.9.14 SPENT FUEL POOL REACTIVITY CONDITION................ 3/4 9 16 FIGURE 3.9 2 SPENT FUEL P0OL RACK MINIMUM BURNUP REQUIREMENTS FOR REGION 2.......................................... 3/4 9 17 FIGURE 3.9 3 SPENT FUEL P00L RACK MINIMUM BURNUP REQUIREMENTS FOR REGION 3.......................................... 3/4 9 18 FIGURE 3.9 4 SPENT FUEL P0OL RACK REGION LOCATIONS................. 3/4 9 19 3/4.9.15 SPENT FUEL P00L C00 LING............................... 3/4 9 20 3/4.9.16 SPENT FUEL P0OL COOLING - DEFUELED.................... 3/4 9 21 l HADDAM NECK XI Amendment No.125.127.158.175,188.193 TS INDEX. DOC

a ._A., a - m.m .t.. , w s _..s.m.- , # . . _ = . .._m_

June 30, 1998

c. INDEX i BASES SECT' ION- PAGE 3/4.0 APPLICABILITY

-3.0.1 .......................................................B3/4 01 3.0.2 .......................................................B3/4 02 3.0.3 DELETED

'3.0.4 .......................................................B3/4 03 4.0.1 .......................................................B3/4 04 4.0.2 .......................................................B3/4 04 4.0.3 .......................................................B3/4 04 4.0.4 .......................................................B3/4 05 4.0.5 DELETED

.4.0.6 DELETED References DELETED ll 3/4.1 DELETED 3/4.2 DELETED l 3/4.3 INSTRUMENTATION 3/4.3.1 DELETED 3/4.3.2 DELETED 3/4.3.3 HONITORING INSTRUMENTATION 3/4.3.3.1 ' DELETED

3/4.3.3.2
DELETED 3/4.3.3.3 SEISMIC INSTRUMENTATION................................B3/4 3 2 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION.........................B3/4 3 2 3/4.3.3.5 DELETED 3/4.3.3.6 DELETED 3/4.3.3.7 RADI0 ACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION.............................B3/4 3 3 3/4.3.3.8 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . .B3/4 3 3 3/4.3.3.9 DELETED 3/4.3.4 DELETED 3/4.4 DELETED t

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HADDAM NECK XIII Amendment No.125,158,193 TS-INDEX. DOC l

June 30, 1998 BASES

. SECT' ION - ' g 3/4.5- DELETED I

3/4.6 DELETED I

3/4.7 PLANT SYSTEMS 3/4.7.1 DELETED 3/4.7.2 DELETED 3/4.7.3 DELETED l

3/4.7.4 DELETED 3/4.7.5 SEALED SOURCE CONTAMINATION........ ..................B3/4 74 3/4.7.6 DELETED j 3/4.7.7 DELETED 3/4.7.8 DELETED 3/4.7.9 DELETED 3/4.7.10 DELETED 3/4.7.11 DELETED 3/4.7.12 DELETED

-HADDAM NECK XIV Amendment No.125.158.171.172.179.193

. TS INDEX. DOC

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L June 30. 1998.  !

9 , INDEX

~ BASES

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p SEC ON- pgg l 3/4.8' DELETED l

L l 3/4.9 REFUELING OPERATIONS l

b 3/4'.9.1 BORON CONCENTRATION....................................B3/4 9 1 3/4.9.2 INSTRUMENTATION........................................B3/4 9 1 1 3/4.9.3- TIME.............................................B3/4 DECAY 91 3/4.9.4' CONTAINMENT BUILDING PENETRATIONS. . . . . . . . . . . . . . . . . . . . . .B3/4 9 1

~3/4.9.5 COMMUNICATIONS.........................................B3/4 9 1

! 3/4.9.6- MANIPULATOR CRANE......................................B3/4 92 3/4.9.7 CRANE TRAVEL SPENT FUEL STORAGE BUILDING.............B3/4 9-2 1 3/4.9.8

- RESIDUAL HEAT REMOVAL AND C0OLANT CIRCULATION..........B3/4 9 2 l l .3/4'.9.9 CONTAINMENT PURGE SUPPLY PURGE EXHAUST AND I

PURGE EXHAUST BYPASS' ISOLATION SYSTEM..................B3/4.9 2 L .3/4.9.10 &

l 3/4.9.11 WATER LEVEL REACTOR VESSEL AND STORAGE P00L..........B3/4 9-3 3/4.9.12 L

' FUEL STORAGE BUILDING AIR CLEANUP SYSTEM...............B3/4 9 3 3/4.9.13- MOVEMENT OF FUEL IN THE SPENT FUEL P00L................B3/4 9 3 ,

3/4.9.14 SPENT. FUEL P00L REACTIVITY CONDITION.................B3/4 9-3

'3/4.9.15 SPENT FUEL P0OL C00 LING. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B3/4 9 3 1 3/4.9.16 SPENT FUEL P00L COOLING DEFUELED.....................B3/4 9 5 l 3/4.10 DELETED l

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'3/4.11 RADI0 ACTIVE EFFLUENTS  !

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3/4.11.1' LIQUID EFFLUENTS l

3/4.11.1.1 CONCENTRATION.........................................B3/4 11 1 3/4;11.1.2 DOSE. LIQUIDS.........................................B3/4 11 1 j 3/4.11.2 GASE0US EFFLUENTS L 3/4.11.2.1 DOSE RATE.............................................B3/4 11 2 3/4.11.2.2 DOSE.'N0BLE GASES.....................................B3/4 L

11 2 3/4.11.2.3 DOSE RADI0 ACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN N0BLE GASES..............B3/4 11 3 3/3.11.3 -TOTAL D0SE............................................B3/4 11 3 L

i l HADDAM NECK XV Amendment No.125.127.158,175.193 l: TS-INDEX. DOC )

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June 30. 1998 1

INDJ.X ADMINISTRATIVE CONTROLS SECTION' PAGE Audits Program Responsibilities............................ 6 9 Records................................................... 6 10 6.6 REPORTABLE EVENT ACTI0N................................... 6 10 L7 DELETED l

6.8 PROCEDURES AND PR0 GRAMS................................... 6 11 1

6.9 REPORTING REQUIREMENTS 6.9.1 Routine-Reports........................................... 6 13 DELETED Ann u a l Report s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 13  !

Annual Radiological Environmental Operating Report........ 614 l

Annual Radioactive Effluent Report. . . . . . . . . . . . . . . . . . . . . . . . 6 15 l

DELETED DELETED Speci al Reports . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 17 i i

6.10 RECORD RETENTION.......................................... 6 17 1

1 6.11 RADIATION PROTECTION PR0 GRAM.............................. 6 18 6.12 HIGH RADIATION AREA....................................... 6 19 1

6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 0DCM).............................. 6 20 6.14 RADI0 ACTIVE WASTE TREATMENT............................... 6 20 6.15 DELETED 6.16 DELETED HADDAM NECK XIX Amendment No.-125.155.158.170.181.193 TS-!NDEX. DOC

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June 30, 1998 ,

INSTRUMENTATION l

1 BsDI0ACTIVELIQUIDEFFLUENTMONITORINGINSTRUMENTATION LIMITING CONDITION FOR OPERATION 1

3.3.3.7 The radioactive liquid effluent monitoring instrumentation l channels shown in Table 3.3 9 shall be OPERABLE with applicable Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The Alarm / Trip Setpoints shall be determined in accordance with methodology and parameters described in the 0FFU h DOSE CALCULATION MANUAL (0DCM).

APPLICABILITY: At all times *.

ACTION:

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a. With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or i declare the channel inoperable, or change the Alarm / Trip Setpoint so it is acceptably conservative.
b. With the number of channels less than the minimum channels operable requirement, take the ACTION shown in Table 3.3 9. Exert best efforts to restore the inoperable monitor to OPERABLE status within 30 days, and, if unsuccessful, explain in the next Annual Effluent Report why the inoperability was not corrected in a timely manner.

Releases need not be terminated after 30 days provided the specified actions are continued.

c. DELETED l

SURVEILLANCE REQUIREMENTS 4.3.3.7.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3 7.

At all times means that channel shall be OPERABLE and in service on a

' continuous, uninterrupted basis, except that outages of monitoring channels are l permitted for a maximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> each time for the purpose of maintenance and performance of required tests, checks, calibrations or sampling.

HADDAM NECK 3/4 3 44 Amendment No.125,170,193 TS3S3.00C

4 June 30, 1998' RADI0 ACTIVE EFFLUENTS DOSE. RADI0 ACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN l

N0BLE GASES LIMITING CONDITION FOR OPERATION-

-3.11.2.3' The dose to any MEMBER OF THE PUBLIC from tritium and radioactive l

. materials in particulate form with half lives greater than 8 days in gaseous 1 effluents released offsite (see Figure 5.11) shall be limited to the  :

following: l

a. During any calendar quarter to less than or equal to 7.5 mrem to any organ;  !
b. During any calendar year to less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radionuclides, radioactive materials in particulate form, or radionuclidos other than noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding' the limit and defines the corrective actions to be taken to reduce the releases during the remainder of the. current calendar quarter and during the remainder of the calendar year so that the cumulative dose or dose commitment to any MEMBER OF THE PUBLIC from such releases during the calendar '

year is within 15 mrem to any organ.

b. DELETED l

SURVEILLANCE REQUIREMENTS -4.11.2.3.1 Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section II of the REMODCM once every 31 days.

4.11.2.3.2 Relative accuracy or conservatism of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in the REM 0DCM.

HADDAM NECK 3/4 11 5 Amendment No. -126,193 TS3511.00C

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BASES 3/4.3.1 THROUGH 3/4.3.2: AND

-PAGES B 3/4 3 1 AND B 3/4 3 la

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f- HADDAM NECK B3/4 3 1 Amendnent No.193

.TSB353.00C l  !

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June 30, 1998-

INSTRUMENTATION .

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BASES l l

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(- 3/4.3.3 MONITORING INSTRUMENTATION i 3/4.3.3.1 DELETED l ,

3/4.3.3.2- DELETED l I

3/4.3.3.3- ' SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to determine the magnitude of a seismic event and evaluate the response of those features important to safety. This capabili-ty is required to permit comparison of the measured response to that used in the design. basis for the facility.

L 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION L The OPERABILITY of the meteorological instrumentation ensures that suffi-cient meteorological data is available for estimating potential radiation

! doses to the public as a result of routine or accidental release of radio-

-active' materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "0nsite Meteorological Programs," February 1972.

I 3/4.3.3.5 DELETED l 3/4.3.3.6 DELETED l L

7 HADDAM NECK B3/4 3 2 Amendment No.426,4 & l93 TSB353.00C

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June 30, 1998 INSTRUMENTATIDE BASES l

3/4.3.3.7 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.3 3.8 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION J l

The radioactive gaseous effluent instrumentation is provided to monitor and ,

control, as applicable, the releases of radioactive materials in gaseous 1 effluents during actual or potential releases of gaseous effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the REM 0DCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consis-tent with the requirements of General Design Criteria 60, 63, and 64 of l Appendix A to 10 CFR Part 50.

3/4.3.3.9 DELETED l 3/4.3.4 DELETED l l

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HADDAM NECK B3/4 3 3 Amendment No.-126.-168,U97193 TSB353. DOC

3 U. S. Nuclear R:gulatory Commission CY-98-199/ Attachment 2/Page 1 I

Attachment 2 Haddam Neck Plant Repaginated Pages 1

October 1998 l

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INDEX June 30, 1998 l

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DEFINITIONS SECTION . pgg 1.0 DEFINITIONS 1.1 ACTI0N..................................................... 1-1 1.2 ANALOG CHANNEL OPERATIONAL TEST............................ 11 1.3 DELETED l 1.4- CHANNEL CALIBRATION........................................ 1-1 1.5 CHANNE L CHECK . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1 1.6 DELETED l 1.7 DELETED l 1.8 CORE ALTERATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 - 2 1.9 DELETED l 1.10 DELETED l 1.11 DELETED l 1.12 FREQUENCY NOTATION....... ................................. 1-2 1.13 DELETED l 1.14. DELETED l 1.15 MEME' 4 / S ; Or THE PUBLIC . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2 1.16 DELEl l 1.17 OPERABLE - OPERABILITY..................................... 13 1.18 OPERATIONAL MODE M0DE.................................... 13 1.19 DELETED l 1.20 DELETED l 1.21 DELETED l 1.22 DELETED l 1.23 RADI0 ACTIVE WASTE TREATMENTS SYSTEMS....................... 13

-1.24 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 00CM)............................... 1 3 1.25 DELETED l I.26 REPORTABLE EVENT........................................... 14 1.27 RHR L00P................................................... 1-4

-1.28 DELETED

-1.29 S ITE B0VNDARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 4 1.30 SOURCE CHECK............................................... 1-4 1.31 DELETED l 1.32 DELETED l

'1.33 DELETED j 1.34 DELETED l 1.35 DELETED l 1.36 DELETED l 1.37 DELETED l TABLE 1.1 FREQUENCY N0TATION......................................... 15

-TABLE 1.2 OPERATI ONAL M0 DES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 6 '

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HADDAM NECK I Amendment No.4 & l93 TS-INDEX. DOC

,m June $J, 1998

.'*. INDEX r-l SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS I l l l

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HADDAM NECK II Amendment No.125.1SS,193 i TS INDEX. DOC

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[ June 30. 1998 s INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE00 mEMENTS SECTION' PAGE 3/4.0 APPLICABILITY 3.0.1 ....................................................... 3/4 0 1 3.0.2 ....................................................... 3/4 0 1 3.0.3- DELETED 3.0.4 ....................................................... 3/4 0 1 4.0.1 ........................................................ 3/4 0 2 4.0.2 ....................................................... 3/4 0 2' 4.0.3 ....................................................... 3/4 0 2 4.0.4 ....................................................... 3/4 0 2 4.0.5 DELETED l 4.0.6 _ DELETED l 3/4.1 DELETED l 3/4.2 DELETED l

3/4.3 INSTRUMENTATION

-3/4.3.1 DELETED l 3/4.3.2 DELETED l 3/4.3.3 MONITORING INSTRUMENTATION l 3/4.3.3.1 DELETED ~ l 3/4.3.3.2 DELETED l

. 3/4.3.3.3 SEISMIC INSTRUMENTATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3 27 TABLE 3.3-5 SEISMIC MONITORING INSTRUMENTATION.................... 3/4 3 28

-TABLE 4.3 4 SEISMIC HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................. 3/4 3 29 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION. . . . . . . . . . . . . . . . . . . . . . . . 3/4 3 30 - l TABLE 3.3 6 HETEOR0 LOGICAL MONITORING INSTRUMENTATION 3/4 3 31 TABLE 4.3 5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................. 3/4 3 32 3/4.3.3.5= DELETED l 3/4.3.3.6 DELETED l 3/4.3.3.7 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION....................................... 3/4 3 44 TABLE 3.3 9 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION....................................... 3/4 3 45 TABLE 4.3 7 RADI0 ACTIVE LIQUID EFFLUENT HONITORING

. INSTRUMENTATION SURVEILLANCE REQUIREMENTS............. 3/4 3 47 3/4.3.3.8 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION....................................... 3/4 3 49 HADDAM NECK III Amendment No.125.179.193

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TS-INDEX.00C-

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June 30, 1998 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION- pgg TABLE 3.3 10 RADI0 ACTIVE GASE0US EFFLUENT HONITORING INSTRUMENTATION....................................... 3/4 3 50 l TABLE 4.3 8 RADI0 ACTIVE GASE0US EFFLUENT MONITORING l

INSTRUMENTATION SURVEILLANCE REQUIREMENTS............. 3/4 3 52  ;

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3/4.4 DELETED l l

3/4.5 DELETED 3/4.6 DELETED l  !

l 3/4.7 -PLANT SYSTEMS l l

3/4.7.1 DELETED l 3/4.7.2 DELETED l 3/4.7.3 DELETED l 3/4.7.4 DELETED l l 3/4.7.5- SEALED SOURCE CONTAMINATION 3/4 7 14 l 3/4.7.6 DELETED l .

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3/4.7.8 DELETED l

.3/4.7.9 DELETED l 3/4.7.10 DELETED l 3/4.7.11 DELETED l 3/4.7.12 DELETED l 3/_4.,8 DELETED l j

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HADOAM NECK IV Amendment No.125.151.158.172.179.193 TS-INDEX. DOC

lg INDEX June 30, 1998 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION .

PAGE 3/4.9 REFUELING OPERATIONS 1 l

3/4.9.1- BORON CONCENTRATION.................................... 3/4 9 1 l 3/4.9.2 INSTRUMENTATION........................................ 3/4 9 2

3/4.9.3 DECAY TIME............................................. 3/4 9 3 i FIGURE 3.9 1 REQUIRED REACTOR HOLD TIME FOR A FULL CORE l 0FFLOAD............................................... 3/4 9 3a 1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS. . . . . . . . . . . . . . . . . . . . . . 3/4 9 4 ~  ;

'3/4.9.5- COMMUNICATIONS......................................... 3/4 9 5 '

3/4.9.6 MANIPULATOR CRANE...................................... 3/4 9 6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING ............ 3/4 9 7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRC'JLATION HIGH WATER LEVEL....................................... 3/4 9 8 LOW WATER LEVEL........................................ 3/4 9 9 I 3/4.9.9 CONTAINMENT PURGE SUPPLY, PURGE EXHAUST, AND l PURGE EXHAUST BYPASS ISOLATION SYSTEM................. 3/4 9 10 3/4 9.10 WATER LEVEL REACTOR VESSEL.......................... 3/4 9-11 3/4.9.11 WATER LEVEL-STORAGE P00L.............................. 3/4 9 12 l 3/4.9.12 FUEL STORAGE BUILDING AIR CLEANUP SYSTEM.............. 3/4 9 13 '

3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL P00L................... 3/4 9-15 3/4.9.14 SPENT FUEL P0OL REACTIVITY CONDITION................ 3/4 9 16 FIGURE 3.9 2 SPENT FUEL P0OL RACK MINIMUM BURNUP REQUIREMENTS FOR REGION 2.......................................... 3/4 9 17 FIGURE 3.9-3 SPENT FUEL P00L RACK MINIMUM BURNUP REQUIREMENTS FOR REGION 3.......................................... 3/4 9 18 FIGURE 3.9 4 SPENT FUEL POOL RACK REGION LOCATIONS........... ..... 3/4 9 19 3/4.9.15 SPENT FUEL P00L C00 LING............................... 3/4 9 20 3/4.9.16 SPENT FUEL P00L COOLING DEFUELED.................... 3/4 9 21 l 3/4.10 DELETED l 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION......................................... 3/4 11-1 l 3/4.11.1.2 DOSE. LIQUIDS......................................... 3/4 11 2 l 3/4.11.2 GASE0US EFFLUENTS

( 3/4.11.9. 1 DOSE RATE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 /4 11 3 1 3/4.11.2.2 DOSE, N0BLE GASES...................... .............. 3/4 11-4 l 3/4.11.2.3 DOSE. RADI0 ACTIVE dATERIAL IN PARTICULATE i FORM AND RADIONUCLIDES OTHER THAN N0BLE GASES......... 3/4 11 5 l 3/4.11.3 TOTAL D0SE............................................ 3/4 11 6 HADDAM NECK V Amendment No.125,175.188.193 Ts.n a x.coc l

c: 1 I June 30, 1998 Lv INDEX ,

BASES SECTION' EAGE 3L00 APPLICABILITY 3.V 1 -

.......................................................B3/4 01 3 s.2 .......................................................B3/4 02

" 0.3

. DELETED

'/.0.4 ...................................................... 83/4 0 3 4.0.1 .......................................................B3/4 0 4 4.0.2 .......................................................B3/4 0 4 4.0.3 .......................................................B3/4 0 4 4.0.4 .......................................................B3/4 0 5 i 4.0.5 DELETED I 1

4.0.6 - DELETED -

- References DELETED 3/4.1 DELETED 3/4.2 DELETED 1

- 3/4.3 INSTRUMENTATION 3/4.3.1 DELETED 3/4.3.2 DELETED 3/4.3.3 MONITORING INSTRUMENTATION

- ? '4.3.3.1 DELETED 3/4.3.3.2 DELETED 3/4.3.3.3 DELETED l l 3/4.3.3.'4- METEOROLOGICAL INSTRUMENTATION.........................B3/4 3-2 i 3/4.3.3.5 DELETED 3/4.3.3.6 - DELETED 3/4.3.3.7 RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION.............................B3/4 3 3 3/4.3.3.8 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION.............................B3/4 3 3 t 3/4.3.3.9_ DELETED L 3/4.3.4 DELETED L - 3/4.4 DELETED L

1, i 3/4.5 DELETED

! 3/4.6 DELETED

' MADDAM NECK VI Amendment No.125.158.193,194 TS.INDEX. DOC p y e m. y - rr y 9 -ene--w

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i* June 30, 1998 o INDEX l

! BASES l

SECTION- pgig 3/4.7 PLANT SYSTEMS l

3/4.7.1 UELETED l 3/4.7.2 DELETED l 3/4.7.3~ DELETED l l .3/4.7.4 DELETED l 3/4.7.5 SEALED SOURCE CONTAMINATION............................B3/4 7 4 3/4.7.6 DELETED l L 3/4.7.7 DELETED- l j 3/4.7.8 DELETED l l l 3/4.7.9 DELETED 3 j 3/4.7.10 DELETED l  !

'3/4.7.11 DELETED l 3/4.7.12 DELETED l 3/4.8 DELETED l

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION....................................B3/4 9 1 3/4.9.2 INSTRUMENTATION........................................B3/4 9 1 3/4.9.3 DECAY TIME.............................................B3/4 9 1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS..................... 83/4 9 1 3/4.9.5 COMMUNICATIONS.........................................B3/4 9 1 3/4.9.6 MANIPULATOR CRANE......................................B3/4 92 3/4.9.7 CRANE TRAVEL SPENT FUEL STORAGE BUILDING.............B3/4 9 2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION..........B3/4 9 2 3/4.9.9 CONTAINMENT PURGE SUPPLY. PURGE EXHAUST. AND PURGE EXHAUST EYDASS ISOLATION SYSTEM. . . . . . . . . . . . . . . . . .B3/4 9 2 3/4.9.10 &

3/4.9.11 WATER LEVEL REACTOR VESSEL AND STORAGE P00L..........B3/4 9 3 3/4.9.12 FUEL STORAGE BUILDING AIR CLEANUP SYSTEM...............B3/4 9 3 3/4.9.13 MOVEMENT OF FUEL IN THE SPENT FUEL P00L................B3/4 9 3 3/4.9.14 SPENT FUEL P0OL - REACTIVITY CONDITION.................B3/4 9 3 3/4.9.15 SPENT FUEL POOL C00 LING................................B3/4 9 3 3/4.9.16 SPENT FUEL P0OL COOLING DEFUELED................ ....B3/4 9-5 l 3/4.10 DELETED l HADDAM NECK VII Amendment No.125.127.158.175.193 l TS INDEX 00C

y June 30. 1998 v INDEX BASES SECTION' PAGE 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION.........................................B3/4 11-1 3/4.11.1.2 DOSE, LIQUIDS.........................................B3/4 11 1 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE.............................................B3/4 11 2

.3/4.11.2.2 DOSE, N0BLE GASES.....................................B3/4 11'2 3/4.11.2.3 DOSE, RADI0 ACTIVE MATEhiAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN N0BLE GASES..............B3/4 11 3 3/3.11.3 TOTAL D0SE............................................B3/4 11 3 HADDAM NECK- VIII Amendment No.125.127.158.175.193 TS-INDEX. DOC x; ,. - _

I June 30, 1998

'- INDEX DESIGN FEATURES SECTION' PAGE

'5.0 DESIGN FEATURES-5.1 SITE 5.1.1 EXCLUSION AREA............................................. 51

-5.1.2 LOW POPULATION Z0NE........................................ 51 FIGURE 5.1 1 EXCLUSION AREA B0UNDARY AND SITE B0UNDARY FOR LIQUID AND GASE0US EFFLUENTS............................... 52 FIGURE 5.1 2 LOW POPULATION Z0NE........................................ 5-3 5.2- DELETED j 5.3 DELETED l

5.4 DELETED l

5.5 METEOROLOGICAL TOWER LOCATI0N.............................. 51 l

-5.6 SPENT FUEL STORAGE l

5.6.1 C R I TI C AL I TY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 4 5.6.2 DRAINAGE................................................... 54 5.6.3 CAPAC I TY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 4 5.7 DELETED l l

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I HADDAM NECK IX Amendment No.-125.175,188,193 TS-INDEX. DOC

r-i June 30. 1998 5 INDEX ADMINISTRATIVE CONTROLS SECTION* PAGE 6.0- ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 61 6.2 ORGANIZATION-6.2.1 DNSITE AND 0FFSITE ORGANIZATIONS........................... 6 1

'6.2.2 FACILITY STAFF............................................. 61

TABLE 6.2 1 MINIMUM SHIFT CREW COMPOSITION............................. 6 3 6.3 FACILITY STAFF OUALIFICATIONS 6-4

'6.4 TRAINING 65 6.5 REVIEW AND AUDIT

<6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)................... 65 Function................................................... 65 C ompo s i t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 5 Al t e r n a t e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 6 Meeting Frequency.......................................... 6 6 Quorum..................................................... 66 Responsibilities........................................... 66 Authority.................................................. 67 Records.................................................... 67 6.5.2 NUCLEAR SAFETY ASSESSMENT BOARD (NSAB) 67 Function................................................... 67 Composition................................................ 68 Al te r n a t e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 8 Meeting Frequency.......................................... 6 8 Quorum..................................................... 68 Revi ew Responsi bili ties . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 9 Audits Program Responsibilities........................... 69 Records................................................... 6 10 i

HADDAM NECK X Amendment No.125.158.181,193 i

TS-INDEX. DOC

I l: June 30, 1998 i+ INDEX ADMINISTRATIVE CONTRQLS

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SECTION-PAGE 6.6 REPORTABLE EVENT ACTI0N................................... 6 10 6.7 DELETED l

'6.8 PROCEDURES AND PR0 GRAMS................................... 6 11 6.9 REPORTING REQUIREMENTS 6.9.1 Routine Reports........................................... 6 13 DELETED I Annu al Repo rt s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 13 Annual Radiological Environmental Operating Report. . . . . . . . 6 14 Annual Radioactive Effluent Report. . . . . . . . . . . . . . . . . . . . . . . . 6 15  !

DELETED  ;

l DELETED Special Reports........................................... 6-17 6.10 RECORD RETENTION.......................................... 6 17 6.11 RADI ATION PROTECTION PR0 GRAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 18 l

6.12 HIGH RADIATION AREA....................................... 6 19 l 1

6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE l CALCULATION MANUAL (REM 0DCM) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 20 4 l

6.14 RADI0 ACTIVE WASTE TREATMENT. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 20 1

6.15 DELETED 6.16 DELETED i

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HADDAM NECK XI Amendment No.125,155.158,170,181,-193 T5-INDEX. DOC

t Juna 30, 1998

  • 4 I

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SECTION 1.0 DEFINITIONS i

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1 HADDAM NECK 11 TSSEC1.00C

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! June 30, 1998 l 1. 0 - DEFINITIONS The defined terms of this section appear in capitalized type and are i

applicable throughout these Technical Specifications.

ACTION l

l 1,1 ACTION shall be that part of a Technical Specification which prescribes remedial measures required under designated conditions.

ANALOG CHANNEL OPERATIONAL TEST L 1.2 An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify 0PERABILITY of alarm, interlock and/or trip functions. The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the alarm, interlock cnd/or Trip Setpoints such that the Setpoints are within the required range and accuracy.

1.3 DELETED l

CHANNEL CALIBRATION 1.4 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions, and may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK 1.5 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

1.6 DELETED l

1.7 DELETED l

l HADDAM NECK 11 Amendment No.125,138,158,193 l

TSSEC1.00C

June 30, 1998 DEFItlITIONS CORE ALTERATION l'. 8 CORE ALTERATION shall be the movement or manipulation of any component within the reactor vessel, with the vessel head removed and fuel in the i

vessel. Suspension of CORE ALTERATION shall not preclude completion of l movement of a component to a safe position.

1 1.9 DELETED l

1.10 DELETED l

1.11 DELETED l

FREQUENCY NOTATION 1.12 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

1.13 DELETED l

1.14 DELETED l

MEMBER (S) 0F THE PUBLIC 1.15 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include emoloyees of the licensee, its contractors, or vendors. Also excluded from this category arre persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

1.16 DELETED l

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l HADDAM NECK 12 Amendment No.425.1A0.193 l

TSSEC1.00C

a.

June 30, 1998 DEFINITIONS OPERABLE OPERABILITY 1.17 A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),

and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).

OPERATIONAL MODE MODE 1.18 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.

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1.20 DELETED l

1.21 DELETED l

1.22 DELETED l

RADI0 ACTIVE WASTE TREATMENT SYSTEMS l l 1.23 RADI0 ACTIVE WASTE TREATMENT SYSTEMS are those liquid, gaseous and solid waste systems which are required to maintain control over radioactive material in order to meet the LC0's set forth in those specifications.

RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 0DCM) 1.24 A RADIOLOGICAL EFFLUENT MONITORING MANUAL (REMM) shall be a manual l containing the site and environental sampling and analysis programs for measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures to individuals from station operation. An 0FFSITE DOSE CALCULATION MANUAL (ODCM) shall be a manual containing the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation Alarm / Trip Setpoints. Requirements of the REM 0DCM are provided in Specification 6.13.

HADDAM NECK 13 Amendment No.424r193 TSSEC1.00C

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June 30, 1998 DEFINITIONS 1.25 DELETED l

REPORTABLE EVENT 1.26 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10CFR Part 50.

RHR LOOP 1.27 An RHR' LOOP consists of a Residual Heat Removal (RHR) pump, a dedicated RHR heat exchanger either from the same train or from the opposite train and i all other necessary ~ piping and components required to receive and cool reactor coolant.

1.28 DELETED l l SITE BOUNDARY 1.29 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

SOURCE CHECK 1.30 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity, i 1.31 DELETED l

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HADDAM NECK 14 Amendment No.125.175,1 & l93

, TSSEC1.00C

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June 30, 1998

.- TABLE 1.1

\

FREQUENCY NOTATION NOTATION FRErl;ENCY

-S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. I D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W At least once per 7 days.

B At least once per 14 days.

H At least once per 31 days.

SW At least once per 42 days.

l Q At least once per 92 days.

SA At least once per 184 days. I R At least once per 18 months. i P Prior to each release.

N.A. Not applicable.

HADOAM NECK 15 Amendment No.4247193 TSSEC1.00C

,;.4..

June 30. 1998 TABLE 1.2 - >

OPERATIONAL H0 DES REACTIVITY  % RATED AVERAGE COOLANT MODE CONDITION. K-fr THERJiAL POWER

  • TEMPERATURE
1. DELETED
2. DELETED
3. DELETED
4. DELETED
5. DELETED 1
6. REFUELING ** less than or equal 0 less than or equal to to 0.94 140 F i

i

  • Excluding decay heat.
** Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

HADDAM NECK 1-6 Amendment No. ML5.193 TSSEC1.00C ,

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