ML20134A080

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Forwards Supplemental Info,Including marked-up Tech Spec Pages Per 850909 Application for Amend to Licenses DPR-53 & DPR-69.Chemistry Procedures Will Be Used to Describe Use of post-accident Sampling Sys During Normal Operations
ML20134A080
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 10/29/1985
From:
BALTIMORE GAS & ELECTRIC CO.
To: Thadani A
Office of Nuclear Reactor Regulation
References
GL-83-37, NUDOCS 8511040159
Download: ML20134A080 (21)


Text

e' si 1

BALTIMORE G AS AND ELECTRIC COMPANY P.O. Box 147 5 B A LTIM O R E. M A R YL A N D 212o 3 '

NUCLEAR POWER DEPARTMENT CALVERT CLIFFS NUCLEAR POWER PL ANT LUSBY. M ARYLAND 20657 October 29,1985 U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 ATTENTION:

Mr. A. C. Thadani, Project Director PWR Directorate #8 Division of PWR Licensing-B

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 SupplementalInformation on Request for Amendment

REFERENCES:

(a)

Letter from A. E. Lundvall, Jr., BG&E, to E. 3. Butcher, Jr., NRC dated September 9,1985, Request for Amendment.

(b)

Letter from A. E. Lundvall, Jr., BG&E, to 3. R. Miller, NRC, dated April 26,1985.

Gentlemen:

This letter forwards supplemental information, including marked up Technical Specification pages changed to incorporate some items discussed earlier with Mr. Jaffe of your staff.

These pages are in substantial agreement with the NRC Guidance Technical Specifications in Generic Letter 83-37, with some minor exceptions. These exceptions are delineated as follows:

EXCEPTION This preposed change includes example procedures which can include the Post Accident Sampling program specifics. The NRC's guidance Technical Specifications in Generic Letter 83-37 do not contain such example procedures.

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8511040159 851029

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Mr. A. C. Thadani October 29,1985 Page 2

- EXPLANATION The wording " plant operation manuals" could be misleading. Calvert Cliffs includes training programs in procedures and instructions separate from _ the plant operations manuals. Additionally, the normal users of the PASS will be chemistry technicians, not operators. Therefore, Chemistry procedures will be used to describe PASS use during normal operations.' Emergency Response Plan Implementing Procedures (ERPIPs) will be used to describe PASS system operations during post-accident conditions. Maintenance procedures will be used to maintain the equipment when necessary.

All of these procedures receive reviews consistent with the requirements of the Quality Assurance (QA) Program in use at Calvert Cliffs, specifically ANSI N18.7-1976. To prevent this misleading terminology from resulting in major unnecessary changes in our QA Program, we are requesting these examples be included in the wording of the Technical Specifications.

For completeness, we are including other marked up Technical Specifications pages, as requested in' references (a) and (b), to ensure the necessary changes to all the Technical Specifications are clearly delineated.

The Determinations of Significant Hazards Considerations in references (a) and (b) are still valid for this change.

AFFECTED PAGES

- UNIT 1 (Attachment 1)

UNIT 2 (Attachment 2)

CHANGE IV IV As Shown

. VII VII As Shown XII XII As Shown XVI XVI As Shown 3/4 3-47 3/4 3-47 Delete 3/4 7-78 3/4 7-70 Delete B3/4 3-3 B3/4 3-3 As Shown B3/47-7 B3/4 7-7 As Shown 6-22 6-22 Add t

Mr. A. C. Thadani October 29,1985 Page 3 Should you have any questions regarding these matters, please feel free to contact us.

Very truly yours, Nb Senior dngineer -

Operational Licensing & Safety LES/sjb

' Attachments cc:

D. A. Brune, Esquire G. F. Trowbridge, Esquire D. H. Jaf fe,' NRC.

T. Foley, NRC T. Magette, DNR

+

s ATTACH 11ENT (1)

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENT PAGE SECTION 3/4.2 POWER DISTRIBUTION LIMITS LINEAR HEAT RATE......................................

3/4 2-1 3/4.2.1 3/4.2.2 TOTAL PLANAR RADIAL PEAKING FACT 0R....................

3/4 2-6 TOTAL INTEGRATED RADIAL PEAKING FACTOR................

3/4 2,9 3/4.2.3 AZIMUTHAL POWER TILT.................................. 3/ 4 2-12 3/4.2.4 3/4.2.5 DNB PARAMETERS.'.......................................

3/4 2-13 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTEkTIVE INSTRUMENTATION....................

3/4 3-1 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM 3/4.3.2 INSTRUMENTATION.....................................

3/.4 3-10 3/4.3.3. MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation..................

3/4 3-25 Incore Detectors......................................

3/4 3-29 Seismic Instrumentation............ _..'.............. 3/4 3-31 Meteorological Instrumentation........................ 3/4 3-34 Remote Shutdown. Instrumentation....................... 3/4 3-37 Post Accident Instrumentation......................... 3/4 3-40 Fire Detectica Instrumentation........................

3/4 3-43 Sdia::th: S::::: Ef'h::t "0 nite

  • g-

. 3/' 3

-I nstrumentati on..............w..................

~

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION.................

3/4 4-1 S ta rtu p an d P owe r..................................... 3 / 4 4-1 Hot Standby...........................................

3/4 4-2 Shutdown..............................................

3/4 4-D g

3/4 4-3 3/4.4.2 SAFETY VALVES 2.......................

3/4.4.3 RE! '

V ALV E S......................................... 3/ 4 4 -4 CALVERT CLIFFS - UNIT I IV Amendment No. 39,53,55.56

.n n-,,

L

. eq= -

mm,

v INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...... 3/4 7-13 3/4.7.3 COMPONENT COOLING WATER SYSTEM....................... 3/4 7-14 3/4.7.4 SERVICE WATER SYTTD1................................. 3/4 7-15 3/4.7.5 SALT WATER SYSTEM....................................

3/4 7-16 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM............ 3/4 7-17 3/4.7.7 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM.........

3/4 7-21 3/4.7.8 SNUB 8 ERS............................................. 3/4 7-2 5 ~

)

3/4.7.9 SEALED SOURCE CONTAMINATION..........................

3/4 7-63 3/4.7.10 WATERTI GHT 000RS..................................... 3/4 7-65 3/4.7.11 FIRE SUPPRESSION SYSTEMS Fi re Suppression Water System........................ 3/4 7-66 Spray and/or Sprinkler Systems....................... 3/4 7-69 Halon System.........................................

3/4 7-72 Fi re Hose S tati ons................................... 3/4 7-73 Yard Fire Hydrants and Hydrant Hose Houses........... 3/4 7-75 3/4.7.12 PENETRATION FIRE BARRIERS............................ 3/4 7-77 bOCT AOCI"CMT CAM."LIN0............................... 3 3/t.7.13 3/4.8 ELECTRICAdPhWERSYSTEMS ej$b k 3/4.8.1 A.C. SOURCES 0pe ra ti ng............................................ 3/ 4 8-1 S h u t d own............................................. 3/ 4 8 - 5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS l

A.C. Dis tribution - Operating........................ 3/4 8-6 i

A.C. Distribution - Shutdown......................... 3/4 8-7 0.C. Distribution - Operating........................

3/4 8-8 D.C. Distribution - Shutdown.........................

3/4 8-11 f

l CALVERT CLIFFS - UNIT 1 VII Amendment No. 25, 87, 64 //3 i

I i

INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURB I NE CY CL E........................................ B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...... B 3/4 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM....................... B 3/4 7-4 3/4.7.4 SERVICE WATER SYSTEM................................. B 3/4 7-4 3/4.7.5 SALT WATER SYSTEM.................................... B 3/4 7-4 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM............ B 3/4 7-4 3/4.7.7 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM......... B 3/4

'-4 7

3/4.7.8 SNU BB ERS............................................. B 3/4 7-5}

3/4.7.9 SEALED SOURCE CONTAMINATION....... g................ B 3/4 7-6 3/4.7.10 WATERTIGHT 000RS..................................... B 3/4 7-6 3/4.7.11 FIgE SUPPRESSION SYSTEMS............................. B 3/4 7-6 3/4.7.12 PENETRATION FIRE BARRIERS............................ B 3/4 7-7 3/4.7.1: ~::p&:= @E:5C...............................:3/477 b \\ ' '. ) g V*Al '

..t 3/4.8 ELECTRICAL POWER SYSTEMS................................ B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.................................. B 3/4 9-1 3/4.9.2 INSTRUMENTATION...................................... B 3/4 9-1 3/4.9.3 DECAY TIME........................................... B 3/4 9-1 3/4.9.4 CONTAINMENT PENETRATIONS............................. B 3/4 9-1

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a a

CALVERT CLIFFS - UNIT 1 XII AmendmentNo.28,//,

i l

l

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.6 REPORTABLE EVENT ACTI0N................................... 6-12 6.7 SAFETY LIMIT VIOLATION.....................................

6-13 6.8 PROCEDURES..,...............................................

6-13 6.9 REPORTING REQUIREE NTS 6.9.1 ROUTINE REP 0RtS..........................................

6-14

~

6.9.2 SPECIAL REP 0RTS..........................................

6-18 m

6.10 RECORD RETENTION..........................................

6-19 6.11 RADIATION PROTECTION PR0 GRAM..............................

6-20 6.12 HIGH RADIATION AREA........................................ 6-20 6.13 ENVIRONMENTAL QUALIFICATION...............................

6-21 1

6.14 SYSTEM INTEGRITY..........................................

6-21 6.15.1 IODINE MONITO RING......................................... 6-22 6.15.2 POST ACnbEMP S Am PUNG 6-22 l

6.16 PROCESS CONTROL PR0 GRAM...................................

6-23 4

h

't 6.17 0FFSITE DOSE CALCULATION MANUAL...........................

6-23 o

s, t

6.18 MAJOR CHANG 8{S TO RADI0 ACTIVE LIOUID. GASEOUS AND

/

SOLID WASTE TREATMENT SYSTEMS...........................

6 8

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CALVERT CLIFFS - UNIT 1 XVI Amendment No. 29 H A4, /pg, l

L

INSTRUMENTATION RADI0 ACTIVE GASEQUS EFFLUENT MONITORING INSTRUMENTATION j

LIMITING CONDITION FOR OPERATION 3.3.3.8 The main vent iodine and particulate sampler 1

ERABL i

APPLICABILITY: All MODES..

ACTION:

a.

With the main vent iodine particulate,

ler inoperable, initiate the preplanned te method a mpling the main vent for the appropriat er(s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:

1.

tither restore th bl ler to OPERABLE status within 7 days of th t

2.

prepare and submit a pursua + to Specifi _4 Report to the Cermtission

~

.9.2 within 30 days following the ev.

utlinj'a ae action taken, the cause of the.

1 erabi a ~

he plans and schedule for restoring ystem tC BLE status.

b.

ions of Specifications 3.0.3 and,3.0.4 are not applicable.,

VEILLAN! RE NTS

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.3.8 e triain vent iodine and particulate sampler shall be demonstrated comparing samples independently drawn frcm the main vent at i

e per month.

t CALVERT CLIFFS - UNIT 2 3/4 3-47 Amencment No.)l2',

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'tLANT SYSTEMS 3

7.13 POST-ACCIDENT SAMPLING LIMI CON 0! TION FOR OPERATION 3.7.13 post-accident sampling system shall be OPERABLE and capa e of processing amples from all of the below listed points:

a.

RCS s le via hot leg b.

RCS samp via low pressure safety injection, and c.

Containment ump sample via low pressure safety in etion.

APPLICA8ILITY: MODES 1, 2, and 3.

ACTION:

With the operability o the post-accide t sampling system less than a.

the LIMITING CONDITIO3 7 OPERATION ecified above, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> initiate the preplan ed altern e method of processing specified sample (s), and ei r:

, - e, 1.

Restore the system d%p 8!$ s !adtr$ within 7 days, or s

2.

Prepare and submit Spe ial Report to the Comission pursuant to Specification 6.9.2 thin 30 days following the event, g

out$ tD6ng the action ken, the catuse of the inoperability, and the plans and schedu for restart g the system to OPERABLE status.

b.

The provisions of Sp cifications 3.0.3 and

.0.4 are not applicable.

SURVEILLANCE REQUIREMEN 1

4.7.13 The post-ac dent sampling system shall be demonst ted OPERABLE at least once per 7,ix 6) months by comparing the results of a C5 sample analyzed by labor ory techniques with the results analyzed b the below listed analyzin equipment:

1.

Boro Analyzer 2.

H rogen and Oxygen Analyzer 3.

pH Analyzer Liquid Radioisotopic Analyzer.

t LVERT CLIFFS - UNIT I 3/4 7-78 Amenoment No. K L

INSTRUMENTATION l

BASES 3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.

This capability is consistent with the reconsnendations of Regulatory Guide 1.97, "Instrumen-tation for Light-Water-Cooled Nuclear Plants to' Assess Plant Conditions During and Following an Accident " December. 1975, and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Reconsnendations."

3/4.3.3.7 FIRE DETECTION INSTRUMENTATION OPERASILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of-fires. This capability is required in order to detect and locate fires in their early stages.

Prompt detection of fires will reduce the poten-e tial for damage to safety related equipment and is an integral element 2

in the overall facility fire protection program.

In the event that a portion of the fire detection instrumentation-is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to operability.

3/4.3.3.8 MACTIVE GASEOUSJMMENT MONITORINGAMTRUMENTATION IODINE Ap6 PARTilulATE SAMPLjf

(

e OPERAB.ITY of e Iodine and Par culate San pler en s that Io e and Par culate amples ca be o ned for ant lysi ring and f

owing an ciden.

The surve e requirements e a high d ree av ilabilit

/The Im e

cln t me et th r quir nt c NURE

?ltem II 1.

The am er's o atipn no a um ini any cci nt y anal (s.

CALVERT CLIFFS - UNIT 1 B 3/4 3-3 Amendment No. 25, 53, //,,

i PLANT SYSTEMS, BASES 3/4.7.12 PENETRATION FIRE BARRIERS The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment.

The penetration fire barriers are a passive element in the facility fire protection program and are subject to periodic inspections.

During periods of time when the barriers are not functional, a continuous fire watch is required to be maintained in the vicinity of the affected barrier until the barrier is restored to functional status.

114.7.13 POST-ACCIDENT SAMPLING SYSTEM The OP TY of the post-Accident Sampling ensures the capability to obta analyze reactor cool nd containment atmos-phere samples during and in an a nt. The surveillance require-mentsensureahighdeg%{

ity.

The Post-Acciden Ifng System was ins to meet the require-ments of NUREG-tem 11.8.3.

The system's opera as not assumed in any ac t analysis.

9

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CALVERT CLIFFS - UNIT 1 8 3/4 7-7 AmendmentNo.26,/JI,

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ADMINISTRATIVE CONTROLS 6.15.1 IODINE MONITORING j

The Ifcensee shall implement a program"wnich will ensure the capability to accurately detemine the airborne iodine concentration in vital areas under accident conditions.

This program shall include the following:

l 1.

Training of personnel, 2.

Procedures for monitoring, and 3.

Provisions for maintenance of s'ampling and analysis equipment.

6.15.2 The following program shall be established, implemented, and

' maintained:

Postaccident Sampling A program

  • which will ensure the capabil,ity to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under' accident conditions..The program shall include the.

following:

(1)

Training gf personnel, (11)

Procedures for sampling and analysis.

(iii)

Provisions for maintenance of sampling and analysis equipment.

l

  • lt is acceptable if the licensee maintains details of the program l

in plant operation manuals (e,., cbistg procedarts, tnalning ostruch'oo4 l

y niaMternex procatan, ERPIPs CALVERT CLIFFS - UNIT I 6-22 Amendment No. //,

~

r ATTACHMENT (2)

'i

_INDEX LIMITING CONDITIONS FOR OPERATION AND SURV SECTION 22LE G

3/4;2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE.....................................

3/4 2-1 3/4.2.2 TOTAL PLANAR RADIAL. PEAKING FACT 0R....

3/4 2-6

\\

3/4.2.3 TOTAL INTEGRATED RADIAL PEAXING FACTOR 3/4 2-9 3/4.2.4 AZIMUTHAL POWER TILT.................................

3/4 2-12 3/4.2.5 DNS PARAMETERS..........................'.............3/4 2-13 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PR0fECTIVE INSTRUMENTATIO 3/4.3.2.

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION...............

3/4 3-10 3/4.3.3 MNITORING INSTRUMENTATION Radiation Monitoring Instrumentation...........

Incore Detectors...............................

3/4 3-25 Seismic kstrumentation..........................

3/4 3-29 3/4 3-31 Meteorolooical Instrumenta tion.......:............

3/4 3-34

^

Remote snutdown Instrumentation......................

3/4 3 37 Post-Accident Instrumenta tion.............

Fire Detection Instrumentation..............

  • Mia*ctive 3:::= !*'h::t.".;..ite-in;;

Ins t rrn; t: t i c;...................................

. 3/' 3 !?

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION.........

S ta rtup and Power...................................

3/4 4-1 3/4 4-1 Hot Standby...........................

Shutdown..............................

3/4 4-2 3/4 4-2a 3/4.4.2 SAFETY VALVES......................

- ~ ~.........

3/4 4-3 3/4.4.3 REL IEF 7RE'/E3...............................

3/4 4 -4 CALVERT CLIFFS - UNIT 2 IV Amendment No. J3, M, 33, EI, a

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...... 3/4 7-13 3/4.7.3 COMPONENT COOLING WATER SY5 TEM.......................

3/4 7-14 3/4.7.4 SERVICE WATER SYSTEM.................................

3/4 7-15 3/4.7.5 SALT WATER SYSTEM.................................... 3/4 7-16 3/4.7.6 CONTROL ROOM EMERGENCY VEN TILATION SYSTEM............ 3/4 7-17 3/4.7.7 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM.........3/4 7-21 3/4.7.8 S NUB 8 ERS............................................. 3/ 4 7 - 2 5 3/4.7.9 SEALED SOURCE CONTAMINATION.......................... 3/4 7-55 3/4.7.10 WATERTIGHT D00RS.....................................

3/4 7-57 3/4.7.11 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System........................ 3/4 7-58.'

Spray and/or Sprinkler Sys tems....................... 3/4 7-61 Halon System.....................................g...

3/4 7-64 Fire Hose Stations...................................

3/4 7-65 Yard Fire Hydrants and Hydrant Hose Houses............ '3/4 7-67 3/4.7.12 PENETRATION FIRE BARRIERS............................

3/4 7-69 3/4.7.13 PO ST AC C I OC"T 0A."P L I."C...............................

3 / 4 7 0 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES i

s..

Ope ra ti ng............................................ 3/ 4 8-1 Shutdown.............................................

3/4 8-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Di stribution - Operating........................ 3/4 8-6 A.C.. Di stribution - Shutdown......................... 3/4 8-7 0.C. Di stribution - Opera ting........................ 3/4 8-8 0.C. Distribution - Shutdown.........................

3/4 8-11 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.p.3 DECAY TIME...........................................

3/4 9-3 1

1

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CALVERT CLIFFS - UNIT 2 VII AmendmentNo.6,JJ,43,A6,/I, L

4 INDEX BASES SLCTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURB I NE CYCLE........................................ B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...... B 3/4 7-3 4

3/4.7.3 COMPONENT COOLING WATER SYSTEM....................... B 3/4 7-4 3/4.7.4 SERVICE WATER SYSTEM.................../............. B 3/4 7-4 3/4.7.5 SALT WATER SYSTEM.................................... B 3/4 7-4 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM............ B 3/4 7-4 3/4.7.7 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM......... B 3/4 7-4 3/4.7.8 SNUBB ERS............................................. B 3/ 4 7-5 3/4.7.9 SEALED SOURCE CCNTAMINATI0N.......................... B 3/4 7-6 3/4.7.10 WATERT IGHT D00RS..................................... B 3/4 7-6 3/4. /.11 FIRE SUPPRESSION SYSTEMS............................. B 3/4 7-6 3/4.7.12 PENETRATION FIRE BARRIERS............................ B 3/4 7-7 3/4.7.13 POST ACCIOCMT Ef.MPLIMO........,.....

....4

....... 3 3.4 7-7 44-3/4.8 ELECTRICAL POWER SYSTEMS................................ B 3/4 B 3/4.9 REFUELINGOPERATIONS 3/4.9.1 BORON CONCENTRATION.................................. B 3/4 9-1 3/4.9.2 INSTRUMENTATION...................................... B 3/4 9-1 3/4.9.3 DECAY TIME........................................... B 3/4 9-1 3/4. 9. 4 CONTAINMENT PENETRATIONS............................. B 3/ 4 9

.ALVERT CLIFFS - UNIT 2 XII Amendment No. 6, JI, II

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 1

6.6 REPORTA8LE EVENT ACTI0N..................................'..

6-12 6.7 SAFETY L IMIT VIOLATION..................................... 6-13 6.8 PRO CEDURES.................................................

6-13 6.9 REPORTING REQUIREMENTS s

6.9.1 ROUTINE REP 0RTS..........................................

6-14 6.9.2 SPECIAL REP 0RTS..........................................

6-18 i

6.10 RECORD RETENTION..........................................

6-19 6.11 RADIATION PROTECf!0N PR0 GRAM..............................

6-20 6.12 HIGN RADIATION AREA....................................... 6-20 6.13 ENVIRONMENTAL QUALIFICATION...............................

6-21 6.14 SYSTEM INTEGRITY..........................................

6-21 6.15.1 IODINE MON ITORING......................................... 6-22 6.15.2 Post Accoeur weavG PROCESS CONTROL PR0 GRAM...................................

6- ?.2 6.16 6-23' 6.17 0FFSITE DOSE CALCULATION MANUAL...........................

6-23

)

L t 1 6.18 MAJOR CHANGE 9 TO RADI0 ACTIVE LIOUID. GASEOUS AND 7

SOLIO WASTE TREATMENT SYSTEMS...........................

6-24

  1. 7

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CALVERT CLIFFS - UNIT 2 XVI Amendnent No.M.36.75. #i L

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[I INSTRUMENTATION

[

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The main vent iodine and particulate sampler PERABLE.

APPLICABILITY: All MODES.

ACTION:

a.

With the main vent iodine and par la pler inoperable, initiate the preplanned alternate method pling the main vent for the appropriate p ter(s)withi hours; and 1.

either restore the sampler to OPERABLE status within,7 d v

or 2.

prepare and submit rt to the Comission pursuant to Specifica within 30 days following the evet outlining th on taken, the cause-of-the inoperat

,and plans and schedule for restoring the syst PE ctatus.

b.

The sions o ications 3.0.3 and 3.0.4 are not applicable S.

m.

_,m,

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.3.3.8 main vent fodine and particulate sampler shall be demonstrated RABLE comparing samples independently drawn from the main vent at to er montn.

CALVERT CLIFFS - UNIT 1 3/4 3-47

. Amendment No II,

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ANT SYSTEMS 3/

.13 POST-ACCIDENT SAMPLING LIMIT CONDITION FOR OPERATION 3.7.13 Th post-accident sampling system shall be OPERABLE and ca ble of processing mples from all of the below listed points:

a.

RCS mple via hot leg b.

RCS sam e via low pressure safety injection, and c.

Containmen sump sample via low pressure safet injection.

APPLICABILITY: MODES 1,

, and 3.

ACTION:

a.

With the operability o the post-a ident sagLl.ing system less than the LIMITING CONDI ON FOR 0 R870" )pecified above, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> initiate e pr anEec algate method of processing specified sp1

's) TI ett'her.

J 1.

Restore the s h0E BLE status within 7 days, or 2.

Prepare and submit a pecial eport to the Commission pursaant to Specification 6.

2 within 0 days following the event, outlining the act' n taken, the ause of the inoperability, and the plans a schedule for re toring the system to OPERABLE statu.

b.

The provisions

. Specifications 3.0.3 an 3.0.4 are not applicable.

SURVEILLANCE RE0VIR ENTS i

s 4.7.13 The ' post accident sampling system shall be demonstrat d OPERABLE at least once per ix (6) months by comparing the results of a RC sample; analyzed by 1 oratory techniques with the results analyzed by t e below-listed anal.ing equipment:

1.

o.ron Analyzer Hydrogen and Oxygen Analyzer 3.

pl{ Analyzer"

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4.

Liquid Radioisotopic Analyzer.

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CAL 7ERT CLIFFS - UNIT 2 3/4 7-70 AmendmentNo.g l

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INSTRUMENTATION

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BASES l'

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3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.

This capability is consistent with the recomendations of Regulatory Guide 1.97, "Instru-mentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions

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During and Following an Accident," December 1975, and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Tenn Recomendations."

3/4.3.3.7 FIRE DETECTION INSTRUMENTATION OPERASILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages.

Prompt detection of fires will reduce the poten-tial for damage to safety related equipment and is an integral element in the overall facilii;y fire protection program.

1 In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to operability.

3/4.3.WIOACTIVE GASJSIMf1FFLUENT MONG9RkWh!NSTRUME N

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i IODNIE AND PAATICULATEEPPLER

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Th ERABI of the dine Particul e Samp' ensur th Iodi nd P,a ulate S es ca e obtained or an.rsis du ng fall ing ccident.

e su illance requi n

ensure i

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degre availability.

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CALVERT CLIFFS - UNIT 2 B 3/4 3-3 Amendment No. JJ, 36,M,

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PLANT SYSTEMS BASES 3/4.7.12 PENETRATION FIRE BARRIERS The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility.

This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment.

The penetration fire barriers are a passive element in the facility fire protection program and are subject to periodic inspections.

During periods of time when the barriers are not functional, a continuous.d barrier until the barrier is res fire watch is required to be maintained in the vicinity of the affecte u.

M 13 POST-ACCIDENT SAMPLING SYSTEM The OPE Y.of the Post-Accident Sampling S ensures the capability to obtain.

analyze reacto. coolant containment atmos-phere samples during and o n an acci The Surveillance Require-mentsensureahighdegrg((

The Post-Accident Sa g System was ins to meet the require-ments of NUREG-0737 I.B.3.

The system's operati s no,t assumed in any accident ysis.

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CALVERT CLIFFS - UNIT 2 3 3/4 7-7 AmendmentNo.JJ,gg, t

w ADMINISTRAT!YE CONTROLS 6.15.1 I0 DINE MONITORING The licensee shall implement a program wnich will ensure the capability to accurately deterinine the airborne iodine concentration in vital areas under accident conditions.

This program shall include the fellowing:

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Training of personnel, 2.

Procedures for monitoring, and 3.

Provisions for maintenance of iampling and anclysis equipmenc.

6.15.2 The following program shall be established, implemented, and r

maintained:

Postaccident Sampling A program

  • which will ensure the capabil.ity to obtain and analyze reactor coolant, radioactive todines and particulates in plant gaseous effluents, and containment atmosphere samples under' accident conditions..The program shall include the, following:

(i)

Training gf personnel, (11)

Procedures for samplin'g and analysis, (111)

Provisions for maintenance of sampling and analysis equipment.

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- *It is acceptable if the licensee maintains details of the program l

in plant operation manuals (e,. cbising precadarth mw,tg nstruefing t

i mMemet precalvres, ERPuh I

CALVERT CLIFFS-UNIT 2 6-22 Amendment No.

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