ML20155G356

Proposed Tech Specs Updating Pages for Amend 194 Re Seismic Monitors

ML20155G356
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:
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ML20155G353	List: ML20155G350 ML20155G356
References
NUDOCS 9811090034
Download: ML20155G356 (3)

Text

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6 BDEX 1

l BASES l SECTION pggg l 3/4.0 APPLICABILITY-l 3.0.1 .......................................................B3/4 01 3.0.2 .......................................................B3/4 02 3.0.3 DELETED 3.0.4 ... ............................................. .....B3/4 0 3 4.0.1 ...................................................... 83/4 0 4 4.0.2 .......................................................B3/4 0 4 4.0.3 .......................................................B3/4 0 4

-4.0.4 .......................................................B3/4 0 5 4.0.5 DELETED 4.0.6 DELETED

! References DELETED 3/4.1- DELETED l

3/4.2 DELETED t

3/4.3 INSTRUMENTATION

-3/4.3.1 DELETED 3/4.3.2 DELETED 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1- DELETED 3/4.3.3.2 DELETED 3/4.3.3.3 DELETED l 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION.........................B3/4 3 2 l 3/4.3.3.5 DELETED 3/4.3.3.6 DELETED l 3/4.3.3.7 RADI0 ACTIVE LIQUID EFFLUENT l MONITORING INSTRUMENTATION.............................B3/4 3 3 l 3/4.3.3.8 RADI0 ACTIVE GASE0US EFFLUENT HONITORING INSTRUMENTATION.............................B3/4 3 3 3/4.3.3.9 DELETED l

3/4.3.4 DELETED I: 3/4.4 DELETED 3/4.5 DELETED 3/4.6 DELETED HADDAM NECK VI Amendment No.125.158,193,194 9811090034 981030 E PDR ADOCK 05000213if P PDR g

O SECTIONS 3.3.1 THROUGH 3.3.3.3:

SECTIONS 4.3.1 THROUGH 4.3.3.3:

TABLES 3.3 1 THROUGH 3.3 5:

TABLES 4.3 1 THROUGH 4.3 4: AND PAGES 3/4 3 1 THROUGH 3/4 3 29 DELETED HADDAM NECK 3/4 3 1 Amendment No.493,194 TS3S3.00C

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INSTRUMENTATION BASES 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 DELETED 3/4.3.3.2 DELETED 3/4.3.3.3 DELETED l 3/4.3.3.4 MU EOR 0 LOGICAL INSTRUMENTATION 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, "Onsite Meteorological Programs," February 1972.

3/4.3.3.5 DELETED l 3/4.3.2.6 DELETED HADDAM NECK. 63/4 3 2 Amendment No.126.-179r193,194

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CONNECTICUT YANKEE ATOMIC POWER COMPANY l HADDAM NECK PLANT 362 INJUN Holt.oW ROAD e EAST HAMPToN, CT 06424-3099 l

October 30,1998 Docket No. 50-213 CY-98-199 Re: 10CFR50.90 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Haddam Neck Plant Supplementalinformation for Proposed License Amendment l Editorial Changes and Tvoograohical Corrections

Background

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Connecticut Yankee Atomic Power Company (CYAPCO) has recently implemented License Amendment 193 0 ). CYAPCO's review of this License Amendment indicates j that some pages contained obvious typographical errors. The NRC Project Manager i was informed of these errors and instructed CYAPCO to supply revised pages to correct the errors. Attachment 1 contains a listing of the corrections made and the revised pages.

This letter also transmits, at the request of the NRC Project Manager, repaginated pages for the Technical Specifications Index and Section 1. These pages are provided in Attac.hment 2 as a supplement to CYAPCO's June 2,1998 submittal <2) requesting changes to Technical Specification 3.3.3.3, Seismic Instrumentation. At the request of the NRC Project manager, index page Vi has been corrected to reflect this deletion of Specification 3.3.3.3.

Please note that the entire HNP Technical Specifications have been changed to the same font for consistency throughout. This was performed with the permission of the NRC Project Manager.

(1) NRC letter from T. L. Fredrichs to R. A Mellor, " Issuance Of Amendment No.193 To Facility Operating License No. DPR-61, Connecticut Yankee Atomic Power Station (TAC NO. M98997),"

dated June 30,1998.

(2) CYAPCO Letter CY-98-084 from R. A. Mellor to the U. S. Nuclear Regulatory Commission.

" Proposed Revision to Technical Specifications - Seismic Monitoring," dated June 2,1998.

1026-3 REV 2-91

U. S. Nuclear Regulatory Commission CY-98-199/Page 2 i

Safety Assessment and Significant Havards Consideration CYAPCO has reviewed the supplemental information provided in this letter in accordance with 10CFR50.92 and concluded that it does not alter the conclusions of l

the safety assessment and significant hazards consideration (SHC}) previously provided in our letters dated May 30,1997,* May 7,1998,* June 2,1998,( and June 18, .

1988* The Commission has pmvided guidance concerning the application of I standards in 10CFR50.92 by providing certain examples (51FR7751, March 6,1986) of Amendments that are not likely to involve an SHC. The proposed changes described in Attachments 1 and 2 are most like example (i) in that they involve correction of typographical errors, and a purely administrative change to consolidate the Index pages.

l Environmental Consideration CYAPCO has reviewed the proposed license amendment against the criteria of 10CFR51.22 for environmental considerations. The proposed changes do not involve an SHC, do not significantly increase the types and amounts of effluents that may be released off-site, and do not significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, CYAPCO concludes that the proposed changes meet the criteria delineated in 10CFR51.22(c)(9) for a categorical exclusion

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from the requirement of an environmentalimpact statement. l Plant Operations Review Committee The Plant Operations Review Committee has reviewed this request and concurs with the above determination.

Nuclear Safety Assessment Board Review The Nuclear Safety Assessment Board has reviewed this request and concurs with the above determination.

(3) CYAPCO Letter CY-97-C06 from T. C. Feigenbaum to the U. S. Nuclear Regulatory Commission,

" Proposed Revision to Operating License and Technical Specifications - Defueled Operating License and Technical Specifications," dated May 30,1997.

(4) CYAPCO Letter CY-98-048 from R. A. Mellor to the U. S. Nuclear Regulatory Commission,

" Supplemental to Defueled License Amendment Spent Fuel Pool Cooling - Defueled." dated May 7,1998.

(5) CYAPCO Letter CY-98-108 from R. A. Mellor to the U. S. Nuclear Regulatory Commission.

" Supplemental Information to Proposed Revision to Operating License and Technical Specifications - Defueled Operating License and Technical Specifications," dated June 18,1998.

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U. S. Nucirr Regut. tory Commission CY-98-199/Page 3 State Notification In accordance with 10CFR50.91(b), CYAPCO is providing the State of Connecticut with a copy of this proposed amendment request.

Commitments There are no commitments contained within this letter.

Schedule Reauired for NRC Anoroval CYAPCO requests that the revised pages, supplied in Attachments 1 and 2, be issued with the License Amendment requested by Reference 2. The revised pages for the Index contained in Attachmer t 2 supersede those contained in Attachment 1.

Conclusion The proposed changes have been reviewed in accordance with 10CFR50.92 and have been determined to not constitute an SHC. In addition, the proposed changes have been reviewed against 10CFR51.22 and it has been determined that the proposed changes meet the criteria for a categorical exemption from requiring an environmental impact statement.

If the NRC Staff should have any questions regarding this submittal, please contact Mr. G. P. van Noordennen at (860) 267-3938.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY

, J R. A. Mellor T Vice President - Operations and Decommissioning Subscribed and sworn to before me this gt* day of October,1998 en n. .n u Date Commission Expires: ,1 s il 9 9

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. U. S. Nucle r Regulatory Commission i

.CY-98-199/Page 4 SAW/saw - l l

Attachments l l

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cc: H. J. Miller, NRC Region 1 Administrator T. L. Fredrichs, NRC Project Manager, Haddam Neck Plant W. J. Raymond, NRC Senior Resident inspector, Haddam Neck Plant E. L. Wilds, Director CT DEP Monitoring and Radiation Division l

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. U. S. Nuclear RIgul: tory Commission CY-98-199/ Attachment 1/Page 1 1

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Attachment 1 Haddam Neck Plant Amendment 193 Revised Pages a

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l October 1998

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, U. S. Nucleir Regul: tory 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.

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, and page number B3/4 9-5 missing.

XV 3/4.11.2.3 NOBEL CASES should be NOBLE GASES.

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" should be " required".

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

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

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

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October 1998

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June 30, 1998 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS I l

4 SECTION EAGE 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 FIGURE 3.9 1 REQUIRED REACTOR HOLD TIME FOR A FULL CORE i 0FFLOAD............................................... 3/4 9 3a I 3/4.9.4 CONTAINHENT BUILDING PENETRATIONS...................... 3/4 9 4 l 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 l PURGE EXHAUST BYPASS ISOLATION SYSTEM................. 3/4 9 10 l 3/4 9.10 WATER LEVEL REACTOR VESSEL.......................... 3/4 9 11 l 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 P0OL REACTIVITY CONDITION................ 3/4 9 16 FIGURE 3.9-2 SPENT FUEL P0OL RACK HIA; MUM BURNUP REQUIREMENTS FOR REGION 2.......................................... 3/4 9 17 FIGURE 3.9 3 SPENT FUEL POOL 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 i 3/4.9.15 SPENT FUEL POOL C00 LING............................... 3/4 9 20 l 3/4.9.16 SPENT FUEL P0OL COOLING DEFUELED.................... 3/4 9 21 l l

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HADDAM NECK XI Amendment No.125,127.158.175.188.193 l

TS !NDEX.00C l

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June 30, 1998 l, INDEX BASES l

SECTION EMiE 3/4.0 APPLICABILITY 3.0.1 .......................................................B3/4 01 l 3.0.2 .......................................................B3/4 02 I 3.0.3 -DELETED 3.0.4 .......................................................B3/4 0 3

'4.0.1 .......................................................B3/4 0 4 4.0.2 .......................................................B3/4 0 4 4.0.3 ...................................................... 83/4 0 4

! 4.0.4 .......................................................B3/4 0 5 l 4.0.5 DELETED 4.0.6 DELETED

! References DELETED

3/4.1 DELETED 3/4.2 DELETED 1

3/4.3 INSTRUMENTATION- I 3/4.3.1 DELETED 3/4.3.2 DELETED 3/4.3.3. MONITORING INSTRUMENTATION 3/4.3.3.1 DELETED 3/4.3.3.2 DELETED l 3/4.3.3.3 SEISMIC INSTRUMENTATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .B3/4 3 2 L 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATI0fl.........................B3/4 3 2 3/4.3.3.5 DELETED i 3/4.3.3.6 DELETED

!- 3/4.3.3.7 RADI0 ACTIVE LIQUID EFFLUENT l MONITORING INSTRUMENTATION.............................B3/4 3 3

! 3/4.3.3.8 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION.............................B3/4 3 3 l

3/4.3.3.9 DELETED 3/4.3.4 DELETED 3/4.4 DELETED HADDAM NECK XIII Amendment No.125.158.193 L

TS INDEX.00C

June 30, 1998

. INDEX ,

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BASES l l

SECTION g 3/4.5 DR FTED l

3/4.6 DELETED l

.3/4.7 PLANT SYSTEMS 3/4.7.1 DELETED l l

3/4.7.2. DELETED l 3/4.7.3 DELETED l 3/4.7.4 DELETED l 3/4.7.5 SEALED SOURCE CONTAMINATION............................B3/4 7 4 I 3/4.7.6 DELETED l 3/4.7.7 DELETED l 3/4.7.8 DELETED l 3/4.7.9 DELETED l 3/4.7.10 DELETED l 3/4.7.11 . DELETED l l 3/4.7.12 DELETED l l

l HADDAM NECK XIV Amendment No.425.158.171.172,179,193

TS-INDEX. DOC l

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June 30, 1998 INDEX BASES l

l SECTION ggiE 3/4.8 DELETED l

3/4.9 REFUELING OPERATIONS 1

L 3/4.9.1 BORON CONCENTRATION................................... 83/4 9-1 i 3/4.9.2 INSTRUMENTATION........................................B3/4 9 1 3/4.9.3 DECAY TIME.............................................B3/4 91 3/4.9.4 CONTAINHENT BUILDING PENETRATIONS......................B3/4 9 1 l 3/4.9.5 COMMUNICATIONS........................................ 83/4 9 1 l 3/4.9.6 MANIPULATOR CRANE......................................B3/4 9 2 l

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 CONTAINHENT PURGE SUPPLY, PURGE EXHAUST, AND PURGE EXHAUST BYPASS 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 H0VEMENT OF FUEL IN THE SPENT FUEL P00L................B3/4 9 3 l

3/4.9.14 SPENT FUEL P0OL REACTIVITY CONDITION.................B3/4 9 3 .

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

3/4.11 RADI0 ACTIVE EFFLUENTS 1

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 GASE0US 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 MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES..............B3/4 11 3 3/3.11.3 TOTAL DOSE ...........................................B3/4 11 3 l.

l HADDAM NECK XV Amendment No.-125,127.158.175.193 TS INDEX. DOC l

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. 1 June 30, 1998 INDEX l

ADMINISTRATIVE CONTROLS I t

1 i SECTION PAGE Audits Program Responsibilities............................ 6 9  :

Records................................................... 6 10 I ll 6.6 REPORTABLE EVENT ACTI0N................................... 6 10 I l

6.7 DELETED l

6.8 PROCEDURES AND PR0 GRAMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 11 6.9 REPORTING REQUIREHENTS

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l 6.9.1 Routine Reports........................................... 6 13

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Ann u al Re po r t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 13 l Annual Radiological Environmental Operating Report. . . . . . . . 614 Annual Radioactive Effluent Report. . . . . . . . . . . . . . . . . . . . . . . . 6 15 l DELETED DELETED I

S pec i a l Repo r t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 17 -

6.10 RECORD RETENTION.......................................... 6 17 l

6.11 RADIATION PROTECTION PR0 GRAM.............................. 6 18 6.12 HIGH RADIATI0N' AREA....................................... 6 19 6.13 RADIOLOGICAL EFFLUENT HONITORING AND QFFSITE DOSE EALCULATION MANUAL (REM 0DCM) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 20 6.14 RADI0 ACTIVE WASTE TREATHENT. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 20 6.15 DELEIED 6.16 DELETED l

l HADDAM NECK XIX Amendment No.125.155.158.170.1817193 TS-INDEX. DOC l

June 30, 1998 l INSTRUMENTATION RADIQACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 1

LIMITING CONDITION FOR OPERATION l 3.3.3.7 The radioactive liquid effluent monitoring instrumentation l

I 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 0FFSITE DOSE CALCULATION MANUAL (00CM).

APPLICABILITY: At all times *.

ACTION:

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 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

SijRVEILLAE E REQUIREMENIS 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 T5353 00C

June 30, 1998 RADI0 ACTIVE EFFLUENTS I

DOSE. RADI0 ACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES l

LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to any MEMBER OF THE PUBLIC from tritium and radioactive materials in particulate form with half lives greater than 8 days in gaseous l effluents released offsite (see Figure 5.11) shall be limited to the following:

a. During any calendar quarter to less than or equal to 7.5 mrem to any organ, i

b. During any calendar year to less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times.

ACIl0N:

a. With the calculated dose from the release of radionuclides,

• radioactive materials in particulate form, or radionuclides 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 REMODCM.

HADDAM NECK 3/4 11 5 Amendment No. 435,193 TS3511.00C

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I BASES 3/4.3.1 THROUGH 3/4.3.2: AND l PAGES B 3/4 3 1 AND B 3/4 3 la

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HADDAM NECK B3/4 3 1 Amendment No. 193 TSB353.00C

June 30, 1998 INSTRUMENTATION BASES 3/4.3.3 MONITORING INSTRUMENTATION-3/4.3.3.1 DELETED l

3/4.3.3.2 DELETED l 1 3/4.3.3.3 SEISMIC INSTRUMENTATION l 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 l the design basis for the facility.

3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that suffi- .

cient it.eteorological 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 "Onsite Meteorological Programs," February 1972.

3/4.3.3.5 DELETED l 3/4.3.3.6 DELETED l HADDAM NECK B3/4 3 2 Amendment No.-126,1797193 TSB353.00C

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INSTRUMENTATION BASES 3/4.3.3.7 RADI0 ACTIVE LIQUID 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 ODCH 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.

1 3/4.3.3.8 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radiosctive materials in gaseous effluents during actual or potential releases of gaseous effluents. The -

Alarm / Trip Setpoints for these , instruments shall be calculated and adjusted l 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 Appendix A to 10 CFR Part 50.

3/4.3.3.9 DELETED l l

3/4.3.4 DELETED l HADDAM NECK B3/4 3 3 Amendment No.W6 M8.-1M r193 l

TSB353 DOC

U. S. Nuclear Regulatory Commission CY-98-199/ Attachment 2/Page 1 Attachment 2 .

Haddam Neck Plant Repaginated Pages October 1998

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INDEX June 30. 1998 l.

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l gINITIONS l

SECTION Egg I o 1.0 DEFINITIONS  !

i 1.1 ACTI0N..................................................... 11 l ANALOG CHANNEL OPEFATIONAL TEST............................

1 1.2 11 1.3 DELETED l 1.4 CHANNEL CALIBRATICi........................................ 11 1.5 CHANNEL CHECK.... ......................................... 1 1 1.6 DELETED l 1.7 DELETED l l 1.8 CORE ALTERATION............................................ 12 l 1.9 DELETED l 1.10 DELETED l 1.11 DELETED l 1.12 FREQUENCY N0TATION......................................... 12 1.13 DELETED l 1.14 DELETED l 1.15 HEMBER(S) 0F THE PUBLIC.................................... 1 2 1.16 DELETED l 1.17 OPERABLE OPERABILITY..................................... 13 1.18 OPERATIONAL MODE H0DE.................................... 1 3 . 1 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 (REH0DCM)............................... 13 1.25 DELETED l 1.26 REPORTABLE EVENT........................................... 14 1.27 RHR L00P................................................... 1 4 1.28 DELETED 1.29 SITE B0VNDARY.............................................. 14 1.30 SOURCE CHECK............................................... 1 4 1.31 DELETED l 1,32 DELETED l 1.33 DELETED l 1.34 DELETED l 1.35 DELETED l

1.36 DELETED l 1.37 DELETED l TABLE 1.1 FREQUENCY NOTATION.. ................ ..................... 1 5 TABLE 1.2 OPERATIONAL M0 DES.......................................... 1 6 HADDAM NECK I Amendment No.4 & l93 TS INDEX.00C

l June 30, 1998

. INDEX l

SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS l

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SECTION py;g l

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INDEX 1 l

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS _

SECTION PAGE i ,

3/4.0 APPLICABILITY l 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 l

4.0.2 ....................................................... 3/4 0 2 i l 4.0.3 ....................................................... 3/4 0 2  :

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3/4.1 DELETED l l 3/4.2 DELETED l

3/4.3 INSTRUMENTATION l l

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 l 3/4.3.3.2 DELETED l I

3/4.3.3.3 SEISMIC INSTRUMENTATION............................... 3/4 3 27 l

TABLE 3.3 5 SEISMIC MONITORING INSTRUMENTATION.................... 3/4 3 28 TABLE 4.3 4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................. 3/4 3 29 3/4.3.3.4 METEOROLOGICAL INSTRJMENTATI0N........................ 3/4 3 30 l l l

TABLE 3.3 6 HETECR0 LOGICAL MONITORING INSTRUMENTATION 3/4 3 31 l 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 1 INSTRUMENTATION....................................... 3/4 3 44 l TABLE 3.3 9 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION....................................... 3/4 3 45 TABLE 4.3 7 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............. 3/4 3 47 3/4.3.3.8 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING i

INSTRUMENTATION....................................... 3/4 3 49 HADDAM NECK III Amendment No. M h 4 & l93 T5-INDD.00C

June 30, 1998

. INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION pef TABLE 3.3 10 RADI0 ACTIVE GASE0US EFFLUENT HONITORING INSTRUMENTATION....................................... 3/4 3 50 TABLE 4.3 8 RADI0 ACTIVE GASE0US EFFLUENT HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMEKTS............. 3/4 3 52 ,

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3/4.6 DELETED {

3/4.7 PLANT SYSTEMS 3/4.7.1 DELETED l 3/4.7.2 DELETED l 3/4.7.3 DELETED l 3/4.7.4 DELETED l 3/4.7.5 SEALED SOURCE CONTAMINATION 3/4 7-14 3/4.7.6 DELETED l 3/4.7.7 DELETED l 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 l

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HADDAM NECK IV Amendment No.125,151.158.172.179.193 l-

TS.INDEX. DOC

INDEX June 30, 1998 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS i

SECTION EAGE 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 FIGURE 3.9 1 REQUIRED REACTOR HOLD TIME FOR A FULL CORE l

0FFLOAD............................................... 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 l HIGH WATER LEVEL....................................... 3/4 9 8 l LOW WATER LEVEL........................................ 3/4 9 9 l 3/4.9.9 CONTAINMENT PURGE SUPPLY, PURGE EXHAUST, AND SYSTEM................. 3/4 9 10 PURGE EXHAUST BYPASS ISOLATION 3/4 9.10 WATF.R LEVEL REACTOR VESSEL...........................3/4 9 11 3/4.9.11 WATER LEVEL STORAGE P00L.............................. 3/4 9 12 1

2/4.9.12 FUEL STORAGE BUILDING AIR CLEANUP SYSTEM.............. 3/4 9 13 L

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 POOL RACK MINIMUM BURNUP REQUIREMENTS FOR REGION 2.......................................... 3/4 9 17 FIGURE 3.9 3 SPENT FUEL POOL RACK HINIMUM 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 POOL C00 LING............................... 3/4 9 20 3/4.9.16 SPENT FUEL POOL C00LIllG DEFUELED. . . . . . . . . . . . . . . . . . . . 3/4 9 21 l

!- 3/4.10 DELETED l 3/4.11 RADI0 ACTIVE EFFLUENTS l

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 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE............................................. 3/4 11 3 l 3/4.11.2.2 DOSE. NOBLE GASES..................................... 3/4 11 4 l 3/4,11.2.3 DOSE, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES......... 3/4 11 5 l 3/4.11.3 TOTAL D0SE............................................ 3/4 11 6 HADDAM NECK V Amendment No.125.175.1SS.193 TS-INDEX.00C

, , ,, , , 7 ,

June 30. 1998 INDEX BASES SECTION EAGE 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 l 3/4.1 DELETED f

3/4.2 DELETED 3/4.3 INSTRUMENTATION L

- 3/4.3.1 DELETED 3/4.3.2 DELETED 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 DELETED 3/4.3.3.2 DELETED 3/4.3.3.3 DELETED l 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 MONITORING INSTRUMENTATION.............................B3/4 3 3

! 3/4.3.3.8 RADI0 ACTIVE GASE0US EFFLUENT l HONITORING INSTRUMENTATION.............................B3/4 3 3 l 3/4.3.3.9 DELETED L 3/4.3.4 DELETED 3/4.4 DELETED

3/4.5 DELETED 3/4,6 DELETED

HADDAM NECK VI Amendment No.125.IES.193.194 TS INDEX. DOC

, , June 30. 1998 l lRDEX BASES j l SECTION pgg 1

3/4.7 PLANT SYSTEMS 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 3/4.7.5 SEALED SOURCE CONTAMINATION............................B3/4 7 4 3/4.7.6 DELETED l 3/4.7.7 DELETED l 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

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 91 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 BYPASS 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 POOL 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 POOL COOLING DEFUELED.....................B3/4 9 5 l l 3/4.10 DELETED l HADDAM NECK VII Amendment No.125,127.158.175,193 TS INDEX. DOC

~

June 30, 1998 ltlDEX i

BASES-SECTION ggig i

. 3/4.11 RADIQACTIVE EFFLUENTS. I 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.............................................83/4 11 2 3/4.11.2.2 DOSE. NOBLE GASES.....................................B3/4 11 2 l 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 t

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J HADDAM NECK VIII Amendment No.125.127.158.175.193 J

TS INDO.00C

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l June 30, 1998 INDEX i

1 I

DESIGN FEATURES SECTION pgg 5.0 DESIGN FEATURES L1 SITE 5.1.1 EXCLUSION AREA............................................. 51 l 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........................................ 53 l

5.2 DELETED l

l 5.3 DELETED l

5.4 DELETED l

5.5 METEOROLOGICAL TOWER L0 CATION.............................. 5 1 l 5.6 SPENT FUEL STORAGE l

l 5.6.1 CRITICALITY................................................ 54 5.6.2 DRAINAGE................................................... 54 l 5.6.3 CAPACITY................................................... 54 5.7 DELETED l

l l

l HADDAM NECK IX Amendment No.-13E.175.188.193 TS.INDEX. DOC

June 30, 1998 INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 61 6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS........................... 6 1 6.2.2 FACILITY STAFF............................................. 61 TABLE 6.2 1 HINIMUM SHIFT CREW COMPOSITION................ ............ 6 3 6.3 FACILITY STAFF QUALIFICATIONS 64 6.4 TRAINING 65 6.5 REVIEW AND AUDII 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)................... 65 Function................................................... 65 .

Composition................................................ 6 5 Alternates................................................. 6 6 Meeting Frequency.......................................... 6 6 Quorum..................................................... 66 Responsibilities........................................... 6 6 Authority.........................................,........ 6 7 Records.................................................... 67 6.5.2 NUCLEAR SAFETY ASSESSMENT BOARD (NSAB) 67 Function................................................... 67 Composition................................................ 6 8 Alternates................................................. 68 Meeting Frequency.......................................... 6 8 Quorum..................................................... 68 Review Responsibilities.................................... 6 9 Audits Program Responsibilities............................ 6 9 Records................................................... 6 10 HADDAM NECK X Amendment No.125,158.181,193 TS-INDEX.00C

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June 30, 1998

~ .. 1}g)EX ADMINISTRATIVE CONTROLS SECTION PAGE 6.6 REPORTABLE EVENT ACTI0N................................... 6 10 6.7 DELE 1ED l

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

6.9 REPORTING REQUIREMENTS 6.9.1 Routine R2 ports........................................... 6 13 DELETED Annual Reports............................................ 6 13 Annual Radiological Environmental Operating Report........ 6 14 Annual Radioactive Effluent Report. . . . . . . . . . . . . . . . . . . . . . . . 6 15 DELETED DELETED S pec i a l Repo rt s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 17 i 6.10 RECORD RETENTION.......................................... 6 17 6.11 RADIATION PROTECTION PR0 GRAM.............................. 6 18 6.12 HIGH RADIATION AREA....................................... 6 19 6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 0DCM) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 20 6.14 RADIOACTIVE WASTE TPEATHENT............................... 6 20 6.15 DELETED 6.16 DELETED HADDAM NECK XI Amendment No.125.155.158.170.181.193 i

TS N ZX. DOC r , .,

June 30, 1998 l

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SECTION 1.0 DEFINITION!.

1 i

l HADDAM NECK 11 l .-

! TSSEC1,00C

. lune 30, 1998  !

1.0 DEFINITIONS l

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications.

ACTION 1.1 ACTION shall be that part of a Technical Specification which prescribes remedial measures required under designated conditions.

ANALOG CHANNEL OPERATIONAL TEST 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 .

OPERABILITY of alarm, interlock and/or trip functions. The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the alarm, interlock and/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 TSSEC1,00C

. _ _ _ _ . . . ._ ._ . . . _ . . . _ _ _ . _-_ . . _ _ - . _ _ . ~ . _ _ _ . . _ _ - _ _ _ _ _

.. )

L June 30, 1998

! DEFINITIONS CORE ALTERATION l

1.8 CORE ALTERATION shall be the movement or manipulation of any component within the reactor vessel, with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe position.

1.9 DELETED l

1.10 DELETED l

l 1.11 DELETED l

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 I

MEMBER (S) 0F THE PUBLIC l 1.15 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded from l l this category are 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 HADDAM NECK- 12 Amendment No.125,140,193

'TSSEC1.00C

_ _. _7 -_7_

June 30, 1998 i DEFINITIONS OPERABLE GPERABILITY 1.17 A system, subsystem, train, component, or device st.all t'a OPERABLE or have OPERABILITY when it is capable of performing its specifired function (s).

l and when all necessary attendant instrumentation, controls, electrical power, l cooling or seal water, lubrication or other auxiliary equipment that are i 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 l

i 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.

1.19 DELETED l 1.20 DELETED j 1.21 DELETED l 1.22 DELETEG l RADIOACTIVE WASTE TREATMENT SYSTEMS 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 environmental 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 REMODCM are provided in Specification 6.13.

HADDAM NECK 13 Amendment No.4267193 TSSEC1 DOC

_._.._._._._.__.7.

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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 l all other necessary piping and components required to receive and cool reactor l coolant.

1.28 DELETED 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 I when the channel scuor is exposed to a source of increased radioactivity.  !

1.31 -DELETED l 1.32. DELETED l

. 1.33 DELETED l

~ 1.34 DELETED l 1.35 DELETED l 1.36 DELETED l 1.37 DELETED' l HADDAM NECK 14 Amendment No.425.175.1SS.193 r

TSSEC1.00C

June 30, 1998 TABLE 1.1 FREQUENCY NOTATION NOTATION FREQUENCY 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 />.

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.

Q At least once per 92 days.

SA At least once per 184 days. -

R At least once per 18 months.

P Prior to each release.

N.A. Not applicable.

l l

HADDAM NECK' 15 Amendment No.42&r193 TSSEC1.00C

June 30, 1998' TABLE 1.2 I

OPERATIONAL MODES REACTIVITY  % RATED AVERAGE C00LWT MODE CONDITION. K-rr TliERMAL POWER

• TEMPERATURE

1. DELETED

2. DELETED

3. DELETED <

i

i. DELETED

5. DELETED ,

6. REFUELING ** less than or equal 0 less than or equal to to 0.94 140 F 1

f

• 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. 426,193  ;

TSSEC1 DOC

1 s

@ l A l 0 l CONNECTICUT YANKEE ATO MIC POWER COMPANY HADDAM NECK PLANT l 362 INJUN HOLLOW FloAD e EAST HAMFroN. CT 06424-3099 l October 30,1998 Docket No. 50-213 CY-98-183 Re: 10CFR50.90 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20553 Haddam Neck Plant Revised License Amendment 193 Technical Specification Pages to Correct Amendment Number on Pages Not Changed bv Amendment 193 Rackground l

' l Connecticut Yankee Atomic Power Company (CYAPCO) has recently implemented i License Amendment 193N. CYAPCO's review of this License Amendment indicates i that some pages were inadvertently marked as Amendment 193 which were not affected by Amendment 193. Some of these pages still displayed revision bars from the original amendment. The NRC Project Manager was informed of this situation and instructed CYAPCO to supply revised pagos to correct the errors. Attachment 1 contains a listing of these pages.

It is our understanding that these pages will be reissued with their original amendment numbers. Please note that the entire HNP Technical Specifications have been changed to the same font for consistency throughout. This was performed with the permission of the NRC Project Manager.

Commitments There are no commitments contained within this letter.

1 (1) NRC letter from T. L. Fredrichs to R. A Mellor,1ssuance Of Amendment No.193 To Facility Operating License No. DPR-61, Connecticut Yankee Atomic Power Station (TAC NO. M98997)."  !

dated June 30,1998.

1026-3 REV 2-91 b

. . - = .- - _ - . - . - - - . _ _ . -

, U. S. Nuclear Regulatory Commission CY-98-183/Page 2 Schedule Reaulred for NRC Anoroval CYAPCO requests that the revised pages supplied in Attachment 1, be issued by I separate letter. These should be coordinated with the issuance of Amendment 194,  !

such that these pages can be incorporated into the Technical Specifications prior to implementation of Amendment 194. 1 If the NRC Staff should have any questions regarding this submittal, please contact Mr. G. P. van Noordennen at (860) 267-3938.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY

'&L>

R. A. Mellor \

Vice President - Operations and Decommissioning SAW/saw .

Attachments cc: H. J. Miller, NRC Region l Administrator T. L. Fredrichs, NRC Project Manager, Haddam Neck Plant W. J. Raymond, NRC Senior Resident inspector, Haddam Neck Plant E. L. Wilds, Director CT DEP Monitoring and Radiation Division

,U. S. Nuclear Regulatory Commission

• CY-98-183/ Attachment 1/Page 1 Attachment 1 Haddam Neck Plant Amendment 193 l Revised Pages .

l I - '. l

! a U. S. Nuclear Regulatory Commission l l CY-98-183/ Attachment 1/Page 2 l

l l PAGE SECTION EXPLANATIONSF DIFFERERGE l l

3/4 3-29 Table 4.3-4 Page was not changed by amendment 193, therefore the page  ;

should show 125 as the applicable amendment number.

3/4 3-31 Table 3.3-6 Page was not changed by amendment 193, therefore the page l should show 125 as the applicable amendment number. '

3/4 3-32 Table 4.3-5 Page was not changed by amendment 193, therefore the page should show 125 as the applicable amendment number.

3/4 3-51 Table 3.3-10 Page was not changed by amendment 193, therefore the page should show 125 as the applicable amendment number.

3/4 9-1 3.9.1 Page was not changed by amendment 193, therefore the page should show 125 as the applicable amendment number.

3/4 9-2 3.9.2.a Page was not changed by amendment 193, therefore the page should show 158 as the applicable amendment number.

3/4 9-3 3.9.3.a Page was not changed by amendment 193, therefore the page should show 188 as the applicable amendment number. -

3/4 9-3a Figure 3.9-1 Page was not changed by amendment 193, therefore the page should show 188 as the applicable amendment number.

3/4 9-4 3.9.4 Page was not changed by amendment 193, therefore the page should show 125 as the applicable amendment number.

3/4 9-5 3.9.5 Page was not changed by amendment 193, therefore the page should show 125 as the applicable amendment number.

3/4 9-6 3.9.6 Page was not changed by amendment 193, therefore the page should show 125 as the applicable amendment number.

3/4 9-7 3.9.7 Struckout amendment number "%w58" should be "158" and not struckout. Page was not changed by amendment 193, therefore the page should show 158 as the applicable amendment number.

3/4 9-8 3.9.8.1 Footnote should appear lower on the page. Page was not changed by amendment 193, therefore the page should show 125 as the applicable amendment number.

9

. U. S, Nuclear Regulatory Commission

'!CY-98-183/ Attachment 1/Page 3 EAGE SECTION EXPLANATION OF DIFFERENCE 3/4 9-9 3.9.8.2 Page was not changed by amendment 193, therefore the page should show 125 as the applicable amendment number.

3/4 9-10 3.9.9 Page was not changed by amendment 193, therefore the page should show 125 as the applicable amendment number.

3/4 0-11 3.9.10 Page was not changed by amendment 193, therefore the page should show 125 as the applicable amendment number. j 3/4 9-12 3.9.11 Page was not changed by amendment 193, therefore the page should show 125 as the applicable amendment number. J 3/4 9-13 3.9.12 Page was not changed by amendment 193, therefore the page should show 187 as the applicable amendment number.  !

3/4 9-14 3.9.12 Page was not changed by amendment 193, therefore the page should show 125 as the applicable amendment number.

l 3/4 9-15 3.9.13 Page was not changed by amendment 193, therefore the page i should show 175 as the applicable amendment number. i 3/4 9-16 3.9.14 Page was not changed by emendment 193, therefore the page should show 188 as the applicable amendment number.

3/4 9-17 Figure 3.9-2 Page was not changed by amendment 193, therefore the page should show 188 as the applicable amendment number.

3/4 9-18 Figure 3.9-3 Page was not changed by amendment 193, therefore the page should show 188 as the applicable amendment number, j l

3/4 9-19 Figure 3.9-4 Page was not changed by amendment 193, therefore the page l should show 188 as the applicable amendment number. I 3/4 9-20 3.9.15 Page was not changed by amendment 193, therefore the page should show 188 as the applicable amendment number.

3/4 11-1 3.11.1.1 Page was not changed by amendment 193, therefore the page should show 125 as the applicable amendment number.

B3/4 9-1 BASES 3.9 Page was not changed by amendment 193, the efore the page should show 188 as the applicable amendment number.

U. S. Nuclear Regulatory Commission l

' CY-98-183/ Attachment 1/Page 4 PAGE SECTION EXPLANATION OF DIFFERENCE .

83/4 9-2 BASES 3.9 Page was not changed by amendment 193, therefore the page should show 158 as the applicable amendment number.

B3/4 9-3 BASES 3/4.9.15 Page was not changed by amendment 193, therefore the page should show PTSCR C-5-97. (This is a Bases change that was '

to be issued with Amendment 193, but was not part of Amendment 193.)

B3/4 9-4 BASES 3/4.9.15 Page was not changed by amendment 193 and missing from the Figure 83/4.9-1 pages received from the NRC. (Should show PTSCR-C-5-97.)

B3/411-1 BASES 3.11 Page was not changed by amendment 193, therefore the page should show 158 as the applicable amendment number.

83/4 11-2 BASES 3.11 Page was not changed by amendment 193, therefore the page should show 125 as the applicable amendment number.

5-2 Figure 5.1-1 Page was not changed by amendment 193, therefore the page should show 125 as the applicable amendment number.

5-3 Figure 5.1-2 Page was not changed by amendment 103, therefore the page should show 125 as the applicable amendment number.

- -. . - . . . - .- - - .. - _- ... -_ -.-.-. = -- - - .

April 26, 1990 TABLE 4.3 4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG CHANNEL CHANNEL CHANNEL OPERATIONAL INSTRUMENTS AND SENSOR LOCATIONS CHECK CALIBRATION TEST

1. Triaxial Servo Accelerometer M R SA (SSA 302) Basemat Cable Vault

2. Digital Cassette Accelerograph M R SA (DCA 300)**

3. Response Spectrum Analyzer M R SA (RSA 50)**

4. Playback System M R SA ,

'(SMR 102)**

5. Seismic Warning Panel M R SA 1 (SWP 300)**

• • All located in the Control Room l

l L HADDAM NECK 3/4 3 29 Amendment No.125 Q OiiD'cCffT~~72flPP T5353 % _ _ .

l

.' \

l l

April 26, 1990 TABLE 3.3 6 METEOROLOGICAL MONITORING INSTRUMEMTATION MINIMUM INSTRUMEMT/ LOCATION OPERABLE

1. Wind Speed

a. Baseline Elev. 33' 1 I

~

b. Nominal Elev. 200' 1 l

2. Wind Direction

a. Baseline Elev. 33' 1

b. Nominal Elev.196' 1 l

3. Air Temper 3ture

a. Baseline Elev. 33' 1

4. Delta T*

a. Nominal Elev. 120' 1 l

1

b. Nominal Elev. 200' 1 i

l

• Delta T is the air temperature of the nominal elevation minus the air temperature at the 33' baseline elevation. I WODAM NECK 3/4 3 31 Amendment No.125 l TS353 DOC 1

j April 26, 1990 TABLE 4.3 5 HETEOR0 LOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT / LOCATION CHANNEL CHECK CHANNEL CALIBRATION i I

1. Wind Speed I 1

a. Baseline Elev. 33' D SA i

b. Nominal Elev. 200' D SA

2. Wind Direction

a. Baseline Elev. 33' D SA

b. Nominal Elev.196' D SA

3. Air Temperature ,

a. Baseline Elev. 33' D SA

4. Delta T*

a. Nominal Elev. 120' D SA

b. Nominal Elev. 200' D SA

• Delta T is the air temperature of the nominal elevation minus the air temperature at the 33' baseline elevation.

HADDAM NECK 3/4 3 32 Amendment No.125 TS3S3 00C

+mm y + -

p---

1 t

April 26, 1990 TABLE 3.3 10 (Continued) l ACTION STATEMENTS ACTION 50 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, releases via the Waste Gas Holdup System may continue provided that best efforts are made to repair the instrument and that prior to initiating the release:

(a) For the tank to be discharged, at least two independent samples of the tank's contents are analyzed: and, (b) The release rate calculations and discharge valve lineups are independently verified by a second individual.

Otherwise, suspend releases from the Waste Gas Holdup System.

Releases from all pathways other than the Waste Gas Holdup '

System may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

, ACTION 51 -

With the number of channels OPERABLE less than required by l the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that samples are continuously collected with auxiliary sampling equipment for periods of seven (7) days and analyzed for principal gamma emitters with half lives greater than 8 days within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the end of the sampling period. Auxiliary sampling shall be established within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of declaring the channel

, INOPERABLE.

I ACTION 52 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that the best efforts l are made to repair the instrument and that the flow rate is estimated once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

3/4 3 51 HADDAM NECK Amendment No.125 Tsasa oot , _ _ _ . _ _ , _ _

._7 April 26, 1990 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 The boron concentration of all filled unisolated portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure a K,rr of 0.94 or less.

APPLICABILITY: H0DE 6*.

l ACTION: l l

With the requirements of the above specification not satisfied, immediately i suspend all operations involving CORE ALTERATIONS or positive reactivity l changes and initiate and continue boration at greater than or equal to 30 gpm of a solution containing a minimum of 14000 ppm boron or its equivalent until K,rr is reduced to less than or equal to 0.94.

SURVEILLANCE REQUIREMENTS 4,9.1.1 The above react 1vity condition shall be determined prior to:

a. Removing or unbolting the reactor. vessel head, and

b. Withdrawal of any control rod in excess of 3 feet from its fully inserted position within the reactor vessel except when control rod drag testing is being performed, at which time the reactivity condition shall be determined prior to the first control rod withdrawn in excess of 3 feet and every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter until completion of the testing.

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

• 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.

HADDAM NECK 3/4 9 1 Amendment No.125 4

TS359.00C

l l

May 27, 1993 REFUELING OPERATIONS i

3/4 9.2 INSTRUMENTATION l

LIMITING CONDITION FOR OPERATION l

3.9.2.a As a minimum, two Source Range Neutron Flux Monitors shall be l

! OPERABLE and operating, each with continuous visual indication in the I control room.and one with audible indication in the containment and control I room when CORE-ALTERATIONS or positive reactivity changes are taking place.

When CORE ALTERATIONS or positive reactivity changes are not taking place,

, at least one Source Range Neutron Flux Monitor shall be OPERABLE and l operating with a visual indication in the control room and audible j indication in the containment. l

! 3.9.2.b As a minimum, two Source Range High Neutron Level Alarms (Containment Evacuation) shall be OPERABLE and operating with a minimum logic to audibly alarm in both the control room and containment of one (1) of two (2).

APPLICABILITY: MODE 6.

ACIl0Ni

a. With one of the above required monitors inoperable or not operating, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

b. With both of the required monitors inoperable or not operating, determine the boron concentration of the Reactor Coolant System 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

SURVEILLANCLREQUIREMENTS 4.9.2 Each Source Range Neutron Flux Monitor shall be demonstrated OPERABLE by performance of:

a. A CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l b. An ANALOG CHANNEL OPERATIONAL TEST within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the l

initial start of CORE ALTERATIONS, and

c. An ANALOG CHANNEL OPERATIONAL TEST at least once per 7 days.

I HADDAM NECK 3/4 9 2 Amendment No.125,147,158 TS359 DOC

1 REFUELING OPERATIONS January 22, 1996 3/4.9.3 DECAY TIME LIMITING CONDITION FOR OPERATION 3.9.3.a The reactor shall be suberitical for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />. l 3.9.3.b Irradiated fuel shall remain in the reactor vessel for at least the time required in Figure 3.91 prior to movement to the spent fuel pool.

APPLICABILIII: During movement of irradiated fuel in the reactor vessel.* l ACTION:

a. With the reactor subcritical for less than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, suspend all operations involving movement of irradiated fuel in the reactor vessel.

b. With the combination of reactor hold time and cooling water temperature in the unacceptable region of Figure 3.91, suspend all operations involving movement of irradiated fuel from the reactor vessel to the spent fuel pool until the combination of reactor hold time and cooling -

water temperature return to the acceptable region of Figure 3.91.

SURVEILLANCE REQUIREMENTS i 4.9.3.1 The reactor shall be determined to have been suberitical for at l least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> by verification of the date and time of subcriticality prior to movement of irradiated fuel in the reactor vessel.

4.9.3.2 Verify that the combination of reactor hold time and cooling water temperature are in the acceptable region of Figure 3.91 prior to and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during transfer of irradiated fuel from the reactor vessel to the spent fuel pool .

l l

• • Specification 3.9.3 b does not apply if less than 53 fuel assemblies are j transferred to the spent fuel pool.

HADDAM NECK 3/4 9 3 Amendment No.4 & l88 15359 00C

i

l. ,

January 22, 1996 so

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I UNACCEPTABLE /

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140 164 188 212 236 260 284 .308 '332 356 380 REQUIRED IN-CORE DECAY TIME OiOURS) l FIGURE 3.9 1 REQUIRED REACTOR HOLD TIME FOR A FULL CORE OFFLOAD HADOAM NECK 3/4 9 3a Amendment No.188 TS359.00C

• 1

\

1 REFUELING OPERATIONS April 26, 1990 3/4.9.4 CONTAINHENT BUILDING PENETRATIONS LIMlIJNG CONDITION FOR OPERATION .

3.9.4 The containment building penetrations shall be in the following status:

a. The equipment hatch installed and secured in place,

b. A minimum of one door in the airlock is closed, and l

c. Each penetration providing direct access from the containment I atmosphere to the outside atmosphere shall be, either:

1) Closed by an isolation valve, blind flange, manual valve, or special device, or

2) Be capable of being closed by an OPERABLE containment purge l supply, purge exhaust, or purge exhaust bypass isolation l valve. '

APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment.

ACTION:

With the requirements of the above s)ecification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building, other than placing an irradiated fuel assembly into a safe storage location.

SURVEILLANCE REQUIREMENTS 4.9.4 Each of the above required containment building penetrations shall be determined to be either in its closed / isolated condition or capable of being closed by an OPERABLE containment purge supply, purge exhaust, or purge exhaust bypass isolation valve or capable of being closed by an OPERABLE airlock door within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment building by:

a. Verifying the penetrations referred to in Specification 3.9.4c are in their closed / isolated condition,

b. Testing the containment purge supply, purge exhaust, and purge exhaust bypass isolation valves in accordance with Specification 4.9.9. and

c. Verifying that at least one of the doors in the airlock is capable of being closed.

HADDAM NECK 3/4 9 4 Amendment No.125 T5359.00C

.- -- . . . . - - _ - - . . - = . - .

April 26, 1990 REFUELING OPERATIONS 3/4.9.5 COMMUNICATIONS l LIMITING CONDITION FOR OPERATION l 3.9.5 Direct communications shall be maintained between the control room

! and personnel at the refueling cavity manipulator crane area.

APPLICABILITY: During CORE ALTERATIONS.

ACTION: -

l With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated l fuel in the containment building other than placing an irradiated fuel assembly into a safe storage location.

SURVEILLANCE REQUIREMENTS 4.9.5 Direct communications between the control room and personnel at the -

refueling cavity manipulator crane area shall be demonstrated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior to the start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during CORE ALTERATIONS.

l l

I l

l I

1 HADDAM NECK 3/4 9 5 Amendment No.125 T5359.00C

l 1

. l s' l REFUELING OPERATIONS April 26, 1990 l l

3/4.9.6 MANIPULATOR CRANE LIMITING CONDITION FT OPERATION ,

l 3.9.6 The manipulator crane and auxiliary hoist shall be used for movement of control rod drive shafts

• or fuel assemblies and shall be OPERABLE with:

a. The manipulator crane used for movement of fuel assemblies having:

1) A mininium capacity of 1650 pounds, and l l

2) An overload cut off limit less than or equal to 175 pounds  ;

above the indicated weight for wet conditions for a stainless I steel clad fuel assembly with a full length RCCA inserted. l 1

b. The auxiliary hoist used for latching and unlatching control rod '

drive shafts having a minimum capacity of 1500 pounds. l APPLICABILITY: During movement of control rod drive shafts or fuel assemblies within the reactor vessel. l ACTION: .

With the requirements for crane and/or hoist OPERABILITY not satisfied. ,

place any fuel assembly or control rod in transit into a safe storage l location and suspend use of the inoperable manipulator crane and/or auxiliary hoist from operations involving the movement of control rod drive l shafts or fuel assemblies within the reactor vessel. l Sil8VEILLMCE REQUIREMENTS 4.9.6.1 Each manipulator crane used for movement of fuel assemblies within the reactor vessel shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations by performing a load test of at least 2063 pounds and demonstrating an automatic load cut off when the crane load exceeds 175 pounds above the indicated weight for wet conditions for a stainless steel clad fuel assembly with a full length RCCA inserted.

4.9.6.2 Each auxiliary hoist used for movement of control rod drive shafts within the reactor vessel shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations. If loads greater than the weight of a stainless steel clad fuel assembly with an RCCA inserted are to be lifted

within the reactor vessel with the auxiliary hoist then a load test will be I

performed for 125% of the weight of the load to be lifted.

• The RCCA's may be attached to the control rod drive shafts during some refueling evolutions.

1 HADDAM NECK 3/4 9 6 Amendment No.125

( TS359.00C

REFUELING OPERATIONS 3/4.9.7 CRANE TRAVEL SPENT FUEL STORAGE BUILDING l )

LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 1650 pounds shall be prohibited from travel over-fuel assemblies in the storage pool.

APPLICABILITY: With fuel assemblies in the storage pool.

ACTION: l

a. With the requirements of the above specification not satisfied, place the crane load in a safe condition,

b. The provisions of Specification 3.0.3 are not applicable.

l l

SURVEILLANCE REQUIREMENTS l

4.9.7 Administrative controls that prevent the travel of loads in excess l of 1650 pounds over fuel assemblies shall be in place prior to lifting a load in excess of 1650 pounds.

l 4

HADDAM NECK 3/4 9 7 Amendment No. 4 & l58 TS359.00C

- ~ _ . . - - . . -

l REFUELING OPERATIONS 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one RHR LOOP shall be OPERABLE and in operation.*

APPLICABILITY: MODE 6, when the water level is greater than or equal to 23 feet above the top of the reactor vessel flange.

ACTION:

With no RHR LOOP OPERABLE and in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR LOOP to OPERABLE and operating status as soon as possible. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere , ,

within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. I SURVEILLANCE REQUIREMENTS l

4.9.8.1 At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> verify at least one RHR LOOP is in operation and circulating reactor coolant at a flow rate of greater than or equal to 2000 gpm.

• - The RHR LOOP may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of the reactor vessel hot legs.

HADOAM NECK 3/4 9 8 Amendment No.125

.TS359.00C

l l

i

. i April 26, 1990 REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDIIION FOR OPERATION 3.9.8.2 Two independent RHR LOOPS shall be OPERABLE, and at least one RHR LOOP shall be in operation.

APPLICABILITY: H00E 6 when the water level is less than 23 feet above the top of the rea:.or vessel flange.

ACTION:

a. With less than the required RHR LOOPS OPERABLE, immediately initiate corrective action to return the required RHR LOOPS to OPERABLE status, or establish greater than or equal to 23 feet of water above the reactor vessel flange, as soon as possible.

b. With no RHR LOOP in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and .

immediately initiate corrective action to return the required RHR LOOP to operation. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCLREQUIREMENTS 4.9.8.2.1 At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> verify at least one RHR LOOP is in operation and circulating reactor coolant at a flow rate of greater than or equal to 2000 gpm.

4.9.8.2.2 The RHR LOOP not in operation shall be determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability.

l HADDAM NECK 3/4 9 9 Amendment No.125

April 26, 1990 REFUELING OPERATIONS 3/4.9.9 CONTAINMENT PURGE #:JjfLY. PURGE EXHAUST. AND PUy3E EXHAUST BYPASS ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 5 3.9.9 The containment purge supply, purge exhaust, and purge exhaust bypass isolation valves shall be OPERABLE.

APPLICABILITY During CORE ALTERATIONS or movement of irradiated fuel within the containment.

ACTION:

a. With the requirements of the above specification not satisfied, immediately sus;>end all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building, other than placing an irradiated fuel assembly into a safe storage location.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.9 The containment purge supply, purge exhaust, and purge exhaust bypass isolation valves shall be verified OPERABLE within 100 hcars prior to the start of and at least once per 7 days during CORE ALTERATIONS and prior to movement of irradiated fuel within containment by verifying that containment purge, bypass or exhaust isolation valves are accessible for manual operatdon or verifying that the associated penetrations are blind flanged.

HADDAM NECK 3/4 9 10 Amendment No.125 75359.00C

1 April 26, 1990 REFUELING OPERATIONS l

l 3/4.9.10 WATER LEVEL - REACTOR VESSEL i l

LIMITING CONDIT1od FOR OPERATION 3.9.10 At-least 23 feet of water shall be maintained over the top of the '

reactor vessel flange.

l '

l AEELICABILITY: During movement of fuel assemblies or control rods within the l containment while in MODE 6.

ACTION:

With the requirements of the above specification not satisfied, place any ,

fuel assembly or control rod in transit into a safe storage location and suspend all further operations involving movement of fuel assemblies or

- control rods within the reactor vessel.

l SURVEILLANCE REQUIREMENTS .

4.9.10 The water level shall be determined to be at least its minimum required depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the start of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during movement of fuel assemblies or control rods.

I l

l s

4 3

HADDAM NECK 3/4 9 11 Amendment No.125 imo ru -

~ -- . .

l

\

April 26, 1990 -

REFUELING OPERATIONS l 3/4.9.11 WATER LEVEL STORAGE POOL LIMITING CONDITION FOR OPERATION l l

3.9.11 At least 20 feet of water shall be maintained over the top of irradiated fuel assemblies seated in the storage racks.

1 APPLICABILITY: Whenever irradiated fuel assemblies are in the storage pool. i ACTION:

a. With the requirements of the above specification not satisfied, l suspend all movements of fuel assemblies and crane operations with  !

loads in the fuel storage areas and restore the water level to  ;

within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. J

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REOUIREMENTS 4.9.11 The water level in the storage pool shall be determined to be at least its minimum required depth at least once per 7 days when irradiated fuel assemblies are in the fuel storage pool.

I HADDAM NECK 3/4 9 12 Amendment No.125 T5359 00C

. REFUELING OPERATIONS January 17, 1996 3/4.9.12 FUEL STORAGE BUILDING AIR CLEANUP SYSTEM LIMITING CONDITION FOR OPERATION 3.9.12 The Fuel Storage Building Air Cleanup System shall be OPERABLE and in operation.

APPLICABILITY: During operations involving movement of fuel within the stora l pool.ge pool or crane operation with loads over the storage ACTION:

a. With the Fuel Storage Building Air Cleanup System inoperable, or not operating, suspend all operations involving movements of fuel within the storage pool or crane operation with loads over the storage pool.* l

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REOUIREMENTS 4.9.12 The Fuel Storage Building Air Cleanup System shall be demonstrated OPERABLE and in operation:

a. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or -

(2) following painting, fire, or chemical release in any ventilation zone communicating with the system by: 1

1) Verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than it and uses the test procedure guidance in Regulatory Positions C.5.a. C.S.c, and C.S.d of Regulatory Guide 1.52. Revision 2, March 1978, and the system flow rate is 4000 c m, 10%:

2) Verifying, within 31 days after removal, that a laboratory analysis of a rearesentative carbon sample obtained in accordance with legulatory Position C.6.b of Regulatory Guide 1.52 Revision 2. March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2 March 1978, for a methyl iodide penetration of less than 10% at test conditions of 86*F, 95% relative humidity atmospheric pressure, and 40 feet / min face velocity in accordance with ASTM D3803: and

3) Verifying a system flow rate of 4000 cfm 10% during system operation when tested in accordance with ANSI N510 1980.

• The above specification does not apply during movement of fuel storage rack modules into or out of the SFP during the Cycle 19 rerack, provided an approved safe loading path is established with no loads ov;.' stored fuel assemblies.

HADDAM NECK 3/4 9 13 Amendment No.12b187 T5359.00C

l l

1

I REFUELING OPERATIONS l

SURVEILLANCE REQUIREMENTS (Continued) l l

b. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying.

within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52 Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2. March 1978, for a methyl iodide penetration of less than 10% at test conditions of 86*F, 95t relative humidity, atmospheric pressure, and 40 feet / min. face velocity in accordance with ASMT D3803. I

c. At least once per 18 months by:

1) Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the system at a flow rate of 4000 cfm 10%, and  !

2) Verifying that the system maintains the spent fuel storage '

pool area at a negative pressure of greater than 0 inch Water Gauge differential relative to the outside atmosphere during system operation.

d. After each complete or partial replacement of a HEPA filter bank, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than it in accordance with ANSI N510 1980 for a DOP test aerosol while operating the system at a flow rate of 4000 cfm 10%: and

e. After each complete or partial replacement of a charcoal adsorber bank, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than it in accordance with ANSI N510 1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 4000 cfm 10%.

HADDAM NECK 3/4 9 14 Amendment No.125 TS359.00C

\

l l

August 16, 1994 REFUELING OPERATIONS 3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL POOL l

LIMIT!NG CONDITION FOR OPERATION 3.9.13 Prior to movement of a fuel assembly in the spent fuel pool, the baron concentration of the pool shall be maintained uniform and sufficient to maintain a boron concentration of greater than or equal to 800 ppm.

APPLICABILITY: Whenever a fuel assembly is moved in the spent fuel pool.

~

ACTION:

With the boron concentration less than 800 ppm, suspend the movement of all fuel in the spent fuel pool.

SURVEILLANCE REQUIREMENT , 4.9.13 Verify that the boron concentration is greater than or equal to 800 ppm within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to any movement of a fuel assembly in the spent fuel pool and every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter.

HADDAM NECK 3/4 9 15 Amendment No.175 T5359 00C

~

l January 22, 1996 l REFUELING OPERATIONS i l

3/4.9.14 SPEMT FUEL POOL REACTIVITY CONDITION I LIMITING CONDITION FOR OPERATION 3.9.14 The Reactivity Condition of the spent fuel pool shall be such that Ke n is less than or equal to 0.95 at all times.

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

l ACTION:

Immediately initiate actions to correct the loading error if the placement of fuel assemblies does not meet the requirements of Figure 3.9 2, Figure 3.9 3. and l

Figure 3.9 4.

l I

l SI)RVEILLANCE REQUIREMENT 4.9.14 Ensure that all fuel assemblies to be placed in the spent fuel pool are within the enrichment and burn up limits of Figure 3.9 2 (Region 2) and Figure 3.9 3 (Region 3) by checking the assembly's design and burn up documentation. Region locations are shown in Figure 3.9 4.

HADDAM NECK 3/4 9 16 Amendment No.W &r188 TS359.00C

1 January 22, 1996 l

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< HADDAM NECK 3/4 9 19 Amendment No.188 T5259.00C

January 22, 1996 REFUELING OPERATIONS 3/4.9.15 SPENT FUEL POOL COOLING ,

LIMITING CONDITION FOR OPERATION 3.9.15 The spent fuel pool cooling system shall be OPERABLE with:

)

a. Both spent fuel pool cooling pumps OPERABLE and at least one spent fuel pool cooling pump and the plate heat exchanger in  ;

operation, and

b. Spent fuel pool temperature less than 150 degrees F.

APPLICABILITY: MODE 6, during transfer and storage of irradiated fuel from the reactor vessel to the spent fuel pool for a full core offload.*

ACTION: With less than the required equipment OPERABLE and in operation or with spent fuel pool temperature greater than 150 degrees F, suspend all operations involving the addition of irradiated fuel to the spent fuel pool and initiate corrective action to restore the spent fuel pool cooling system to OPERABLE status as soon as possible.

SURVEILLANCE REQUIREMENTS 4.9.15.1 Prior to movement of irradiated fuel to the spent fuel pool, verify that both spent fuel pool cooling pumps are lined up to provide flow to the plate heat exchanger.

4.9.15.2 At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, verify that at least one spent fuel pool cooling pump is running.

4.9.15.3 At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, verify that the spent fuel pool temperature is less than 150 degrees F.

• Specification 3.9.15 does not apply if less than 53 fuel assemblies are transferred to the spent fuel pool.

HADDAM NECK 3/4 9 20 Amendment No.188 T5359 DOC

i April 26, 1990 l 3/4.11 RADIQACTIVE EFFLUENTS i

3/4.11.1 LIQUID EFFLUENTS CONCENTRATION i LIMITING CG!DITION FOR OPERATION l

3.11.1.1 The concentration of radioactive material released from the site (see Figure 5.11) shall not exceed the concentrations specified in '

10 CFR Part 20, Appendix B. Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall not exceed 2 x 10 microCi/ml total activity.

APPLICABILITY: At all times. ,

ACTION:

With the concentration of radioactive material released from the site exceeding the above limits, restore the concentration to within the above .

limits within 15 minutes.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed in accordance with the sampling and analysis program specified in Section I of the REMODCH.

4.11.1.1.2 The results of the radioactive analysis shall be used in 4

accordance with the methods of Section II of the REMODCM to assure that the concentration of the point of release are maintained within the limits of Specification 3.11.1.1.

HADDAM NECK 3/4 11 1 Amendment No. 125 TS3511. DOC

- - - . _ , . ~ . . - - _ __ .

January 22, 1996 3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that: (1) the reactor will remain subcritical during CORE ALTERATIONS, and (2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. These limitations are consistent with the initial conditions assumed for the baron dilution incident in the accident analyses. A value of 0.94 or less for K,rr is required for this accident. For a core configuration of all rods in an additional 0.05 K,rr penalty is required to account for a heavy load crushing the core into a more reactive configuration. q 3/4.9.2 INSTRUMENTATION The OPERABILITY of the Source Range Neutron Flux Monitors ensures that monitoring capability is available to detect changes in the reactivity condition of the core. Redundant monitoring capability is required to .

detect changes in the reactivity condition of the core during fuel movement. I 3/4.9.3 DECAY TIliE The minimum requirement for reactor subcriticality prior to movement of irradiated assemblies in the reactor vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products.

The minimum requirement for reactor hold time prior to movement of irradiated fuel from the reactor vessel to the spent fuel pool ensures that sufficient decay time has elapsed for adequate spent fuel pool cooling should a failure occur to the cooling system. The reactor hold time is a function of cooling water temperature. The required decay time assumes a conservative maximum transfer rate of six assemblies per hour. These decay times are consistent with the assumptions used in the safety analysis.

l 3/Lo.4 CONTAINMENT t3UILDING PENETRATIONS The requirements on containment building penetration closure and OPERABILITY l ensure that a release of radioactive material within containment will be restricted from leakage to the environment. The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization l potential while in the REFUELING MODE.

1/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling cavity manipulator crane area personnel can be promptly informed of significant l changes in the facility status or core reactivity conditions during CORE ALTERATIONS.

HADDAM NECK B3/4 9 1 Amendment No.426.188 im em

= nJ-A.-da & .Jm 44. _m .4 _1

^

l i

. REFUELING OPERATIONS BASES 3/4.9.6 MANIPULATOR CRANE 1

The OPERABILITY requirements for the manipulator cranes ensure that: (1) manipulator cranes will be used for movement of control rod drive shafts and fuel assemblies, (2) each crane has sufficient load capacity to lift a drive shaft or fuel assembly, and (3) the core internals and reactor vessel are protected from excessive lifting forces in the event they are inadvertently engaged during lifting operations.

3/4.9.7 CRANE TRAVEL SPENT FUEL STORAGE BUILDING l

The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped: (1) the activity release will be limited to that contained in single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the safety analysis.

314.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one RHR LOOP be in operation ensures that: (1) -

sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor vessel below 140 F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the core to minimize the effect of a boron dilution incident and prevent boron stratification.

The requirement to have two RHR LOOPS OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR LOOP will not result in a complete loss of residual heat removal capability. With the reactor vessel head removed and 23 feet of water above the reactor vessel flange, a large heat sink is available for core cooling. Thus. in the event of a failure of the operating RHR LOOP, adequate time is provided to initiate emergency procedures to cool the core.

3/4.9.9 CONTAINMENT PURGE SUPPLY. PURGE EXHAUST. AND PURGE EXHAUST BYPASS ISOLATION SYSTEM The OPERABILITY of this system er.sures that the containment vent and purge penetrations can be isolated upon detection of high radiation levels within the containment. The OPERABILITY of this system is reqaired to restrict the release of radioactive material from the containment atmosphere to the environment.

HADDAM NECK B3/4 9 2 Amendment No.126.158

. December 11, 1997 PTSCR C 5 97 REFUELING OPERATIONS BASES 3/4.9.10 and 3/4.9.11 WATER LEVEL REACTOR VESSEL AND STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the safety analysis.

3/4.9.12 FUEL STORAGE BUILDING AIR CLEANUP SYSTEM The limitations on the Fuel Storage Building Air Cleanup System ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal 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 safety analysis.

ANSI N510 1980 will be used as a procedural guide for surveillance testing.

3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL POOL The limitations of this specification ensure that, in the event of any fuel handling accident in the spent fuel pool, K,rr will remain s 0.95, 3/4.9.14 SPENT FUEL POOL REACTIVITY CONDITION The limitations described by Figures 3.9 2, 3.9 3, and Figure 3.9 4 ensure that the reactivity of fuel assemblies introduced into the spent fuel racks. I with no credit taken for soluble boron in the pool, are conservatively within the assumptions of the safety analysis.

3/4.9.15 SPENT FUEL POOL COOLING The limitations on the Spent Fuel Pool Cooling System ensure there is sufficient capacity to remov decay heat produced by the stored fuel elements (1019 assemblies) and maintain the bulk pool temperature below 150 F with a maximum heat load as shown in Fig. B3/4.9 1.

Requiring both SFP cooling pumps to be OPERABLE provides backup capability in l the event the operating pump fails. In the event of a complete loss of forced cooling, the time to boil, excluding the effect of evaporation, is greater than 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> based on current heatup calculations. Only makeup would be required to maintain pool inventory.

l HADDAM NECK B3/4 9 3 Amendment No.125.175.188

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3/4.11 RADI0 ACTIVE EFFLUENTS g l BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radioactive materials released.in liquid waste effluents from the site will

- be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within: (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe 135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

3/4.11.1.2 DOSE. LIOUIDS l This specification is provided to implement the requirements of Sections .

II.A, III.A. and IV,A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". The dose calculation methodology and parameters in the REMODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the REMODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided ein Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose cf Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977, and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

HADDAM NECK B3/4 11 1 Amendment No. 12&r158 T583511.00C

1 1

l September 26, 1995

. RADI0 ACTIVE EFFLUENTS PTSCR No. C 5 95 BASES 3/4.11.2 GASE0US EFFLUENTS 3/4.11.2.1 DOSE RATE l This specification is provided to ensure that the dose rate at anytime from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for all areas offsite. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, l Table II. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exmsure of an individual offsite to annual average concentrations exceeding t1e limits specified in Appendix B. Table II of 10 CFR Part 20 (10 CFR 20.106(b)). For individuals who may at times be within the site boundary, the occupancy of '

that individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to 500 mrem / year to the total body or to less than or equal to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid or other organ dose rate above background to a child to less than or equal to 1500 mrem / year from l inhalation.

3/4.11.2.2 DOSE. NOBLE GASES This specification is provided to implement the requirements of Sections II.B., III.A and IV.A of A]pendix I, 10 CFR Part 50. The Limiting Condition for Operation implements t1e guides set forth in Section II.B of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conform with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109,

" Calculational of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light Water Cooled Reactors." Revision 1, July 1977.

The ODCM equations provided for determining the air doses at the site boundary are based upon utilizing successively more realistic dose calculational methodologies. More realistic dose calculational methods are used whenever simplified calculations indicate a dose approaching a substantial portion of the regulatory limits. The methods used. in order are, previously determined air dose per released activity ratio. historical meteorological data and actual radionuclide mix released, or real time meteorology and actual radionuclides released.

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