ML20094P335

Proposed Tech Specs Clarifying Source Change Definition

ML20094P335
Person / Time
Site:	Millstone
Issue date:	11/21/1995
From:	NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
Shared Package
ML20094P334	List: B15435, Application for Amend to License NPF-49,revising Ts,To Clarify Definition of Source Check ML20094P335
References
NUDOCS 9511290048
Download: ML20094P335 (11)

Text

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ggg 03/24/94 RASES suum thu 3/4.0 APPLICABILITY............................................... B3/40-1 3/4.1 REACTIVITY CONTROL SYSTEMS

~3/4.1.1 soRATION CONTR0L.......................................... B3/41-1 3/4'.1.2 soRATION SYSTEMS.......................................... B3/41-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES................................

B3/41-3a l 3/4.2 POWER DISTRIBUTION L1MITS................................... B3/42-1 3/4.2.1 AXIAL FLUX DIFFERENCE..................................... B3/42-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR and RCS FLOW B 3/4 2-3 RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR.........

3/4.2.4 QUADRANT POWER TILT RATI0. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B3 3/4.2.5 DNB PARAMETERS............................................ B3/42-5 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM INSTRUMENTATION and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION........................................... B3/43-1 3/4.3.3 MONITORING INSTRUMENTATION................................ B3/43-3 3/4.3.4 TURBINE OVERSPEED PROTECTION. . . . . . . . . . . . . . . . . . . . . . . l. . . . .

1 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION.............B3/44-1 3/4.4.2 SAFETY VALVES............................................. B3/44-2 3/4.4.3 PRESSURIZER............................................... B3/44-2 3/4.4.4 RELIEF VALVES............................................. B3/44-2 3/4.4.5 STEAM GENERAT0RS.......................................... B3/44-3 3/4.4.6 REACTOR COOLANT SYSTEM LEAXAGE . . . . . . . . . . . . . . . . . . . . . . . . . . . . B,3/44-4 3/4.4.7 CHEM I ST RY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B3 3/4.4.s SPECIFIC ACTIVITY......................................... B3/44-5 i 3/4.4.9 PRESSURE /TEMPERATURELIMITS............................... B3/44-7 I

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! MILLSTONE -JINIT 3 xiit Amendment No. JJ. .

-8181 - 9511290048 951121 i o dedo PDR ADOCK 05000423 I __R .m _ . , PDR , , _

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' JAN 311986' DEFIN2TIONS g * , l SITE 80 NOARY 7

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

SLAVE RELAY TEST 1.32 A SLAVE RELAY TEST shall be the energization of each slave relay and

' verification of OPERABILITY of each relay. The SLAVE RELAY TEST shal? include a continuity check, as a minimum, of associated testable actuation devices.

SOURCE CHECK 1.33 A SOURCE CHECK shall be the qualitative asse nt o n el re n w .n M r y anal <annor is_exnosed to radiation.

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1.34 A STAGGERED TEST BASIS shall consist of:

a. A test schedule for n syste'ns, subsystems, trains, or other designated components obtained by dividing the specified test I interval into n equal subintervals, and

b. The testing of one system, subsystem, train, or other designated /Ejs component at the beginning of each subinterval. '

THERMAL POWER 1 1.35 THERMAL POWER shall be the total reactor core heat. transfer rate to the reactor coolant.

TRIP ACTUATING DEVICE OPERATIONAL TEST  !

1.36 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the

. Trip Actuating Device and verifying OPERABILITY of alarm, interlock and/or j trip functions. The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include

, adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required Setpoint within the required accuracy.

UNIDENTIFIED LEAKAGE -

1.37 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE

} or CONTROLLED LEAXAGE.

l UNRESTRICTED AREA 4

1.38 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY l 4

to which access is not controlled by the licensee for purposes of protection of '

individuals from exposure to radiation and radioactive materials, or any area c i within the SITE BOUNDARY used for residential quarters or for industrial, t commercial, institutional, and/or recreational purposes.

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. JAN 31 1986 l l ,

INSTRUMENTATION - .

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i 3/4.3.3.8 LOOSE-PART DETECTION SYSTEM (

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The OPERABILITY of the Loose-Part Detection System ensures that sufficien

) capability is available to detect loose metallic partsThe in the Reactor System j allowable and avoid or mitigate damage to Reactor System components.

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. cut-of-service times and surveillance requirements are c I the Primary System of Light-Water-Cooled Reactors," May 1981.

3/4.3.3.9 RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATIO j >

The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials TheinAlare/

liquid effluents during actual or potential releases of liquid effluents.

j Trip Setpoints for these instruments shall beThecalculated a alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.

j OPERABILITY and use of this instrumentation is consistent with the requirements The  ;

l of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.q7 purpose of tank level indicating devices is to assure the detection and con i

of leaks that if not controlled could potentially result in the transport of -gg,g , _

radioactive materials to UNRESTRICTED AREAS. ef som  :

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! 3/4.3.3.10 RADIDACTIVE GASEOUS EFFLUENT MONITORING 'INSTRUMENTAT The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluen

l. during actual or potential releases of gaseous effluents.

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methodology and parameters in the REMODCM to ensu The OPERABILITY and use lj occur prior to exceeding the Ifmits of 10 CFR Part 20.of The sensitivity of this instru Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.any ent release requirements of Specification 3.11.2.2 shall be such that concen-

!j trations as low as 1 x 10 8 pCi/cc are measurable.

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3/4.3.4 TURBINE OVERSPEED PROTECTION b This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERAl l

and will protect the turbine from excessive overspeed. excessivel l )

generate potentially damaging missiles which could impact and damage safety-related components, equipment, or structures.  ?

L MILLSTONE - UNIT 3 8 3/4 3-6 o W.7

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Uvrg/tT' 70 //)(6 $ 3[ } 4 Tables 4.3 8 and 4.3-9 allow the option d using ionizing radiation or light radiation l i ,

3 (i.e. an LED) to source ched the emuent radiation monitors. Allowancel i

a light source is based on an intomai NRC memorandum from LJ. Cunningham to J.H. Joyner, D.M. Collins, LR. Greger, AB. Beach, and G.P. Ydas dated December 6,1990 and titled, " Relaxation d the Definition d Source Check Under i the Licensee's ODCM." The NRC memorandum allowed the uso d an LED ba l I on the following conditions, all which are applicable at Millstone:

- 1. The emuont monitors are used only for detecting radiation which activates an I

i alarm setpoint and are not used as the primary means W quantifying smuent 4

releases.

2. When monitored activity is sufreiently high the monitor reading is cross checked j

with grab sample (Chemistry) results.

- 3. Except for the use d an LED and grab sample cross 4meks when activity is sufficiently high there are no other practical means d source checking the emuent radiation monitors.

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RADI0 ACTIVE EFFLUENTS JAN 311986 8ASES l DOSE RATE (Continued)

sufficiently low to compensate for any increase in the atmospheric diffusion 1

! factor above that for the SITE 80VNDARY. The specified release rate limits re-

! strict, at all times, the corresponding gamma and beta dose rates above back-ground to an individual at or beyond the SITE BOUNDARY to less than or equal 4 to 500 arems/ year to the.whole body or to less than or equal to 3000 arees/ year j to the skin. Thesp release rate limits also testrict, at all times, the cor-1 responding thyroid Idose rate above background to a child via the ceW44hch'M

! pathway to less tMn or equal to 1500 aress/ year. /* ^~d

! oa M oi%t onw j 3/4.11.2.2 DOSE - N0BLE GASES 4

j This specification is provided to implement the requirements of Sections II.B. III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition  !

for Operation implements the guides set forth in Section 11.8 of Appendix I.

} The ACTION statements provide the required operating flexibility and at the 4 same time implement the guides set forth in Section IV.A of Appendix ! to assure 1

! that the releases of radioactive material in gaseous affluents will be kept I

! "as low as is reasonably achievable." The Surveillance Requirements implement i the requirements in Section III.A of Appendix I that conform with the guides of 2

Appendix ! be shown by calculational procedures based on models and data such

{ that the actual exposure of an individual through appropriate pathways is j unlikely to be substantially underestimated. The dose calculation estaD11shed in the REMODCM for calculating the doses due to the actual release rates of radio- -

! active noble gases in gaseous affluents will be consistent with the methodology

provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from

Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance i with 10 CFR Part 50, Appendix I" Revision 1, October 1977 and Regulatory j Guide 1.111 " Methods for Estimating Atmospheric Transport and Dispersion of

Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors,"

j Revision 1," July 1977.

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j The REMODCM equations provided for determining the air doses at the site 4 boundary are based on utilizing successively more realistic dcse calculational methodolcgies. More realistic dose calculational methods are used whenever simplified calculations indicate a dose approaching a substantial portion of the regulatory limits. The meth>ds used, in order, are previously determined air dose per released activity ratio, historical meterological data and actual radionuclide six released, or real time meteorological and actual radionuclides .

released.

3/4.11.2.3 DOSE - RADIO 10 DINES. RADI0 ACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES This specification is provided to implement the requirements of Sections II.C. III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C 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 .

MILLSTONE - UNIT 3 8 3/4 11-2 e6s -

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Docket No.'50-423 [

B15435 [

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Attachment 2  :

r Millstone Nuclear Power Station, Unit No. 3 Proposed Technical Specifications Revision Source Check Definition Retyped Technical Specifications L

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INDEX BASES SECTION IEE 3/4.0 APPLICABILITY ....................... B 3/4 0-1 l

3/4.1 REACTIVITY CONTROL SYSTEMS l 3/4.1.1 B0 RATION CONTROL . . . . . . . . . . . . . . . . . . . . . B 3/4 1-1 3/4.1.2 B0 RATION SYSTEMS . . . . . . . . . . . . . . . . . . . . . B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES . . . . . . . . . . . . . . . . B 3/4 1-3a i

3/4.2 POWER DISTRIBUTION LIMITS ................. B 3/4 2-1 3/4.2.1 AXIAL FLUX DIFFERENCE .................. B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR .... B 3/4 2-3 5 B 3/4 2-5 3/4.2.4 QUADRANT POWER TILT RATIO ................

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3/4.2.5 DNB PARAMETERS . . . . . . . . . . . . . . . . . . . . . . B 3/4 2-5 3/4.3 INSTRUMENTATION

i. 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM INSTRUMENTATION AND 1 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION ..................... B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION . . . . . . . . . . . . . . . . B 3/4 3-3 3/4.3.4 TURBINE OVERSPEED PROTECTION . . . . . . . . . . . . . . . B3/43-7l 3/4.4 REACTOR COOLANT SYSTEM  !

l 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION ...... B 3/4 4-1 l 3/4.4.2 SAFETY VALVES ...................... B 3/4 4-2 3/4.4.3 PRESSURIZER ....................... B 3/4 4-2 3/4.4.4 RELIEF VALVES ...................... B 3/4 4-2 3/4.4.5 STEAM GENERATORS . . . . . . . . . . . . . . . . . . . . . B 3/4 4-3 l 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE . . . . . . . . . . . . . . B 3/4 4-4 3/4.4.7 CHEMISTRY ........................ B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY .................... B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS ............... B 3/4 4-7 MILLSTONE - UNIT 3 xiii Amendment No. pp, pp, o4m I

DEFINITIONS SITE BOUNDARY  !

I 1.31 The SITE BOUNDARY shall be that line beyond which the land is neither j owned, nor leased, nor otherwise controlled by the licensee.- [

SLAVE RELAY TEST  !

1. ,

i 1.32 A SLAVE RELAY TEST shall be the energization of each slave relay and  !

4 verification of OPERABILITY of each relay. The SLAVE RELAY TEST shall include. l a continuity check, as a minimum, of associated testable actuation devices.  :

l SOURCE CHECK i i 1.33 A SOURCE CHECK shall be the qualitative assessment of channel response j when the channel sensor is exposed to radiation. The source check radiation l may be in the form of ionizing radiation or light radiation (i.e., from an i l LED). ,

STAGGERED TEST BASIS i l

1.34 A STAGGERED TEST BASIS shall consist of

i l a. A test schedule for n systems, subsystems, trains, or other

, designated components obtained by dividing the specified test  :

interval into n equal subintervals, and

! b. The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.

THERMAL POWER l.35 THERMAL POWER shall be the total reactor core heat transfer rate to the j reactor coolant.

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TRIP ACTUATING DEVICE OPERATIONAL TEST

i 1.36 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Actuating Device and verifying OPERABILITY of alarm, interlock and/or

. trip functions. The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include  :

adjustment, as necessary, of the Trip Actuating Device such that it actuates '

at the required Setpoint within the required accuracy. i UNIDENTIFIED LEAKAGE 1.37 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.

UNRESTRICTED AREA i 1.38 An UNRESTRICTED AREA shall be any area at or beyond the SITE B0UNDARY to '

! which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the' SITE BOUNDARY used for residential quarters or for industrial, 2 commercial, institutional, and/or recreational purposes.

MILLSTONE - LNIIT 3 1-6 Amendment No.

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4 INSTRUNENTATION BA!ES

. 3/4.3.3.8 LOOSE-PART DETECTION SYSTEM The OPERABILITY of the Loose-Part Detection System ensures that sufficient capability is available to detect loose metallic parts in the Reactor System and avoid or mitigate damage to Reactor System components. The allowable out-of-service times and surveillance requirements are consistent with the ,

recommendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-cooled Reactors," May 1981.

3/4.3.3.9 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation-is provided to monitor and control, as applicable, the releases of radioactive materials in liquid -

effluents during actual or potential releases of liquid effluents. The Alarm /

Trip Setpoints for these instruments shall be calculated and adjusted in ac-cordance 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 consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The purpose of tank level indicating devices is to assure the detection and control of leaks that if not controlled could potentially result in the transport of radioactive materials to UNRESTRICTED AREAS.

Table 4.3-8 and 4.3-9 allow the option of using ionizing radiation or light radiation (i.e., an LED) to source check the effluent radiation monitors.

Allowance for use of a light source is based on an internal NRC memorandum from L. J. Cunningham to J. H. Joyner, D. M. Collins, L. R. Greger, A. B. Beach, and G. P. Yuhas dated December 6,1990, and titled, " Relaxation of the Definition of Source Check Under the Licensee's ODCM." The NRC memorandum allowed the use of an LED based on the following conditions, all which are applicable at Millstone.

1. The effluent monitors are used only for detecting radiation which activates an alarm setpoint and are not used as the primary means of quantifying effluent releases.

2. When monitored activity is sufficiently high, the monitor reading is cross-checked with grab sample (Chemistry) results.

3. Except for the use of an LED and grab sample cross-checks when activity is sufficiently high, there are no other practical means of source checking the effluent radiation monitors.

3/4.3.3.10 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the REM 0DCM to ensure that the alarm / trip will occur prior to ex:eeding the limits of 10 CFR Part 20. The OPERABILITY and use MILLSTONE - UNIT 3 8 3/4 3-6 Amendment No.

0427

l INSTRUNENTATION BASES 3/4.3.3.10 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (Continued) of this instrumentation is consistent with the requirements of General Design

Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The sensitivity of 4

any noble gas activity monitors used to show compliance with the gasecus efflu-ent release requirements of Specification 3.11.2.2 shall be such that concen-

, trations as low as 1 x 10* pci/cc are measurable. ,

See last' paragraph of 3/4.3.3.9 Bases for source check clarification. l l

3/4.3.4 TURBINE OVERSPEED PROTECTION .

1

. This specification is provided to ensure that the turbine overspeed protection _ instrumentation and the turbine speed control valves are OPERABLE .

and will protect the turbine from excessive overspeed. Protection from turbine

! excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage .

j safety-related components, equipment, or structures.

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NILLSTONE - UNIT 3 B 3/4 3-7 Amendment No.

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RADI0 ACTIVE EFFLUENT I ' BASES.

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i' DOSERATE(Continued) sufficiently low to compensate for any increase in the atmospheric diffusion

factor above that for the SITE BOUNDARY. The specified release rate limits re-L strict, at all times, the corresponding gamma and beta dose rates above back-i ground to an individual at or beyond the SITE BOUNDARY to less than or equal

to 500 mress/ year to the whole body or to less than or equal to 3000 arems/ year to the skin. These release rate limits also restrict, at all times, the cor-

responding thyroid or any other organ dose rate above background to a child via j the inhalation pathway to less than or equal to 1500 mrems/ year.

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l 3/4.11.2.2 DOSE - NOBLE GASES This specification is >rovided to implement the requirements of Sections II.B, I I III.A and IV.A of Appendix -, 10 CFR Part 50. The Limiting Condition

! for Operation implements the guides set forth in Section II.B of Appendix 1.

! The ACTION statements provide the required operating flexibility and at the j .same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluent will be kept i "as low as is reasonably achievable." The Surveillance Requirements implement i the requirements in Section III.A of Appendix I that conform with the guides of ,

i A>pendix I be shown by calculational procedures based on models and data such '

i ttat the actual exposure of an individual through appropriate pathways is i unlikely to be substantially underestimated. The dose calculation established i in the REM 00CM for calculating the doses due to the actual release rates of radio-l active noble gases in gaseous effluent will be consistent with the methodology

! provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from l Routine Releases of Reactor. Effluent 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 Effluent in Routine Releases from Light-Water Cooled Reactors, Revision 1," July 1977.

l The REMODCM equations provided for determining the air doses at the site boundary are based on utilizing successively more realistic dose calculational methodologies. More realistic dose calculational methods are used whenever I 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 meteorological and actual radionuclides released.

3/4.11.2.3 DOSE - RADIOI0 DINES. RADI0 ACTIVE MATERIAL IN PARTICULATE 1 FORM AND RADIONUCLipES OTHER THAN N0BLE GASES This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions

for Operation are the guides set forth in Section II.C of Appendix 1. The 4

ACTION statements provide the required operating flexibility and at the same 1 time implement the guides set forth in Section IV.A of Appendix I to assure i

i i MILLSTONE - LNGIT 3 8 3/4 11-2 Amendment No.

one