ML20148D317

Proposed Tech Specs 3/4.4.5 Re Reactor Coolant Sys Specific Activity

ML20148D317
Person / Time
Site:	Brunswick
Issue date:	05/23/1997
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20148C872	List: BSEP-97-0222, Application for Amends to Licenses DPR-71 & DPR-62,revising Action Statements a.1 & a.2 of TS 3/4.4.5 by Reducing Max Allowed Reactor Coolant Specific to Activity ML20148D317
References
NUDOCS 9705300151
Download: ML20148D317 (13)

Text

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ENCLOSURE 5 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 NRC DOCKET NOS. 50-325 AND 50-324 OPERATING LICENSE NOS. DPR-71 AND DPR-62 1

- REQUEST FOR LICENSE AMENDMENTS REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY PAGE CHANGE INSTRUCTIONS UNIT 1 Removed page Inserted page 3/4 4-10 3/4 4-10 B 3/4 4-3 8 3/4 4-3 PAGE CHANGE INSTRUCTIONS UNIT 2 Removed page Inserted page 3/4 4-10 3/4 4-10 , .

B 3/4 4-3 B 3/4 4-3 i

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9705300151 970523 [l PDR ADOCK 05000324 .

p PDR v b.. -

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ENCLOSURE 6 l BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 NRC DOCKET NOS. 50-325 AND 50-324

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l ""TUfSW""*"C!Nda'a^"f!/S R

l REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY L

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MARKED-UP TECHNICAL SPECIFICATION PAGES - UNIT 1 t

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REACTOR CCCLANT SYSTEM 3/4.4.5 SPECIFIC ACTIVITY LIMITING CONDfTION FOR 0?IRATION 3.4.5 The specific ac:ivity cf the reactor coolan: shall be limited to:

a. Less than er equal to 0.2 aci/ gram COSE EQUIVALENT I-131, and l

b. less than or equal to 100/5 aci/gra=.  ;

APPLICA5!LITY: OPERATIONAL CONDITIONS 1, 2, 3, and 4 -

ACTION:

.. a. In OPERA!!ONAL CONDIT*0N 1, 2, and 3, vi:h the specific activity of the reactor coolant;

1. Cre er :h - 0.2 uCi/ gram DOSE EQUIVALENT I-131 but less than or l equal to uCi/ gram, operation may continue for up to

.0 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided that opera: ion under these conditions shall

~

not exceed 10 percen: of the unit's total yearly operating time. The provisions of Specifica: ion 3.0.4 are not applicable. _

REVBE

2. Creater than 0.2 uCi/ gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or greater than uCi/ gram, be in 4: least HOT SHUTDOWN vich the main steam line isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3. Creater than 100/5 .Ci/ gram, be in 4: least HOT SHUTDOWN vich ene main s: cam line isolation valves :losed within 12 nours and in COLD SHUTDOWN within :ne nex: 24 nours,

b. In CPERATIONAL CDNDIT!ON 1, 2, 3, or 4,

.. Vi h the specific ac:ivi:y of the pri.ary coolan: greater than l 0.2 aci/ gram DOSE EQUIVALINT I-131 or grea:er :han i 100/E aci/ gram. perform :ne sampling anc analysis requiremen:s of Item 4e of Table 4.4.5-1 a lear: once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> until ene specific ac:ivi:y of the primary cociant is res:ored to vi:hin its limits. In lieu of a License Event Repor:, prepare and ,

submi: to the Commission vi:nin 30 days, pursuant to i Specifica: ion 6.9.2, a Special Report that defines the results of :he specific activity analyses and the time duration unen the specific activi:y of the coolan: exceeded 0.0 aci/ gram DOSE l EQUIVALENT I-131 togeener v:th the below adcicional information.

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/

3R'.'N5!!r - ;N:71 ]/ 4-10 Amendment No. 83 l

REACTOR COOLANT SYSTEM BASES The surveillance requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.

In order to reduce personnel radiation exposure. chemical decontamination of portions of the reactor coolant system may be performed during shutdown. During the chemical decontamination process. the injection of chemical solvents may cause the reactor coolant system conductivity and chloride measurements to increase above the limits. The solvents that are selected for use in performing the chemical decontamination proce.ss are selected and evaluated to ensure their chemical reactivity will not adversely impact components or the structural integrity of the reactor coolant system.

Because decontamination activities are performed at temperatures significantly less than normal operating temperatures, the chemical reactivity of these solvents will not increase the likelihood of stress corrosion occurring nor affect those stress corrosion cracks that may already be present.

3/4 4.5 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the 2-hour thyroid and whole body doses resulting from a main steam line failure outside the containment during steady state operation will not exceed small fractions of the dose guidelines in 10CFR 100. Permitting operation to continue for limited time periods with higher specific activity levels accommodates short-term iodine spikes which may be associated with power level

~ hanges, c and is based on the fact that a steam line failure during these short time periods is considerably less likely. Operation at the higher activity levels, therefore, is restricted to a small fraction of the unit's total operating time. The upper limit of coolant iodine concentration during short-term iodine spikes ensures that the thyroid dose fr m ~~ 4 will not exceed 10 CFR Part 100 dose guidelines. Or GDC-/i dvfg lhi / Nf Gdrtl R& CPrahts, Information obtained on iodine spiking will be u ., e i

parameters associated with spiking phenomena. A reduction in frequency of 1 isotopic analysis following power changes may be permissible. if justified by the data obtained.

Closing the main steam line isolation valves prevents the r.elease of activity to the environs should the steam line rupture occur. The surveillance requirements provide adequate assurance that excessive specific activity levels in the reactor coolant will be detected in sufficient time to take corrective action.

l

3/4 4.6 PRESSURE / TEMPERATURE LIMITS l All components in the Reactor Coolant System are designed to withstand the effects of cyclic loads due to system temperature and pretsure changes.

These cyclic loads are introduced by normal load transients, reactor trips.

and start-up and shutdown operations. The various categories of load cycles used for design purposes are,provided in Section 4.2 of the FSAR. During BRUNSWICK - UNIT 1 8 3/4 4-3 Amendment No. 180 l l

l l

l' ENCLOSURE 7 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 NRC DOCKET NOS,50-325 AND 50-324 OPERATING LICENSE NOS. DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY l

L l

?

i l

l i

I i ' MARKED-UP TECHNICAL SPECIFICATION PAGES - UNIT 2 i

I l

I

l l

REACTOR COOLANT SYSTEM 3/4.4.5 SPECIFIC ACTIVITY ,

LIMITINC CONDITION FOR OPERATION 3.4.5 The specific activity of the reactor coolant shall ba limited to:

a. less than or equal to 0.2 uCi/ gram DOSE EQUIVALENT I-131, and l

b. less than or equal to 100/5 uCi/ gram. l APPLICA3ILITY: OPERATIONAL CONDITIONS 1, 2, 3, and 4 ACTION:

l a. In OPERATIONAL CONDITION 1, 2, and 3, vich the specific activity of

! the reactor coolant; I -

l 1. Creater than 0.2'uci/gr DOSE EQUIVALENT I-131 but less chan or equal to . uCi/ gram, operation may continue for h, ) up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided that operation under these conditions

_. shall not exceed 10 percent of the unit's total yearly operating l

- time. The provisions of Specification 3.0.4 are not applicable.

REVl56  ;

2. Creater than 0.2 uCi/ gram DOSE EQUIVA'ENT L I-131 for more than '

~

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous' time interval or greater than

. pCi/ gram, be in at least HOT SEUTDOWN wi,th the main steam-line isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3. Creater than 100/E uCi/ gram, be in at least HOT SHUTDOWN with l the main steam line isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWK within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. In OPERATIONAL CONDITION 1, 2, 3, or 4,

1. With the specific activity of the primary coolant greater than 0.2 uCi/ gram DOSE EQUIVALENT I-131 or greacer than 100/E uCi/ gram, perform the sampling and analysis requirements l of Item 4b of Table 4.4.5-1 at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> until the specific activity of the primary coolant is restored to within its limits. In lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to l

Specification 6.9.2, a Special Report that defines the results ~

of the specific activity analyses and the time duration when the specific activity of the coolant exceeded 0.2 uCi/ gram DOSE EQUIVALENT'I-131 together with the below additional Information.

k t'

f.I BRUNSWICK - UNIT 2 3/4 4-10 Amendment No. 110 1

. I REACTOR COOLANT SYSTEM BASES l

The surveillance requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to '

take corrective action.

In order to reduce personnel radiation exposure. chemical decontamination of portions of the reactor coolant system may be performed during shutdown. During the chemical decontamination process, the injection of chemica! solvents may cause the reactor coolant system conductivity and l ' chloride measurements to increase above the limits. The solvents that are

! selected for use in performing the chemical decontamination process are j selected and evaluated to ensure their chemical reactivity will not adversely impact components or the structural integrity of the reactor coolant' system.

Because decontamination activities are performed at temperatures significantly less than nor.1al operating temperatures, the chemical reactivity of these i solvents will not increase the likelihood of stress corrosion occurring nor affect those stress corrosion cracks that may already be present.

l 2/4 4.5 SPECIFIC ACTIVITY -

The hmitations on the specific activity of the primary coolant ensure that -the 2-hour thyroid and Wie body doses resulting from a main steam line failure outside the containmt it during steady state operation will not exceed small fractions of the dose guidelines in 10CFR 100. Permitting operation to continue for limited time periods with higher specific activity levels l accommodates short-term iodine spikes which may be associated with power level l changes, and is based on the fact that a steam line failure du' ring these short time periods is considerably less likely. Operation at the higher activity levels, therefore. is restricted to a small fraction of the unit's total i

operating time. The upper limit of coolant iodine concentration durin short-term iodine spikes ensures that the thyriod dose f 1 a ai will not exceed 10 CFR Part 100 dose guidelines. or GDc-1 0.f t - liJf [ar ,

Cgnfrd/ RGdm G era pf' Information obtained on iodine spiking will be _ as ne parameters associated with spiking phenomena. A reduction in frequency of isotopic analysis following power changes may be permissible, if justified by j the data obtained.

Closing the main steam.line isolation valves prevents the release of activity to the environs should the steam line rupture occur. The surveillance requirements provide adequate assurance that excessive specific activity levels in the reactor coolant will be detected in sufficient time to take corrective action.

3/4.4.6 PRESSURE / TEMPERATURE LIMITS All components in the Reactor Coolant System are designed to withstand

' the effects of cyclic loads due to system temperature and pressure changes.

These cyclic loads are introduced by normal load transients, reactor trips.

! and start-up.and shutdown operations. The various categories of load cycles

! used for design purposes are provided in Section 4.2 of the FSAR. During BRUNSW CK -. UNIT 2 8 3/4 4-3 Amendment No. 211 I

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

l l

! I 1

l ENCLOSURE 8 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2  ;

i t NRC DOCKET NOS. 50-325 AND 50-324 OPERATING LICENSE NOS. DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS ~

REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY l

l L

1 l

TYPED TECHNICAL SPECIFICATION PAGES - UNIT 1 2

9 i

REACTOR COOLANT SYSTEM i 3/4.4 5 SPECIFIC ACTIVITY , j

! I l LIMITING CONDITION FOR OPERATION

j. L3 4.5 The specific activity of the reactor coolant shall be limited to:

a; less than or equal to 0.2 pCi/ gram DOSE EQUIVALENT I-131. and ]

l l b. less than or equal to 100/ 5 .uCi/ gram. l APPLICABILITY: OPERATIONAL CONDITIONS 1. 2. 3, and 4 l -ACTION:

L i a. In OPERATIONAL CONDITION 1. 2. and 3. with the specific activity of_

! the reactor coolant:

i l

1. Greater than 0.2 pCi/ gram DOSE EQUIVALENT I-131 but less than or equal to 3.0 pCi/ gram, operation may continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> I l provided that o)eration under these conditions shall not exceed 10 percent of t1e unit's total yearly operating time. The-l provisions of Specification 3.0.4 are not applicable, i

2. Greater than 0.2 pCi/ gram DOSE EQUIVALENT I-131 for'more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or greater than 3.0 gCi/ gram, be in at least HOT SHUTDOWN with the main steam .. !

-line isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3. Greater than 100/ 5 vCi/ gram, be in at least HOT SHUTDOWN with i

the main steam line isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. In OPERATIONAL CONDITION 1. 2. 3. or 4, l

1. With the specific activity of the primary coolant greater than 0.2 gCi/ gram DOSE EQUIVALENT I-131 or greater than 100/ 5 pCi/ gram, perform the sampling and analysis requirements  !

I of Item 4b of Table 4.4.5-1 at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> until the specific activity of the primary coolant is restored to within i its limits. In lieu of a Licensee Event Report prepare and .

l' submit to the Commission within 30 days, pursuant to i S)ecification 6.9.2._ a Special Report that defines the results of tie specific activity analyses and the time duration when the specific activity of the coolant exceeded 0.2 gC1/ gram DOSE EQUIVALENT I-131 together with the below additional information.

i i

BRUNSWICK - UNIT 1 3/4 4-10 Amendment No.

i

, _ _ , , , - - - , . J

l REACTOR COOLANT S,Y_SJE l

BASES The surveillance requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.

In order to reduce personnel radiation exposure. chemical

! decontamination of portions of the reactor coolant system may be performed l during shutdown. During the chemical decontamination process, the injection

, of chemical solvents may cause the reactor coolant system conductivity and l -

chloride measurements to increase above the limits. The solvents that are selected for use in performing the chemical decontamination process are selected and evaluated to ensure their chemical reactivity will not adversely impact components or the structural integrity of the reactor coolant system.

Because decontamination activities are performed at temperatures significantly less than normal operating temperatures the chemical reactivity of these solvents will not increase the likelihood of stress corrosion occurring nor affect those stress corrosion cracks that may already be present.

3/4.4.5 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the 2-hour thyroid and whole body doses resulting from a main steam line failure outside the containment during steady state operation will not exceed small fractions of the dose guidelines in 10CFR 100. Permitting operation to continue for limited time periods with higher specific activity levels accommodates short-term iodine spikes which may be associated with power level changes, and is based on the fact that a steam line failure during these short time periods is considerably less likely. Operation at the higher activity levels, therefore, is restricted to a small fraction of the unit's total l operating time. The upper limit of coolant iodine concentration during short-term iodine spikes ensures that the thyroid dose from a steam line failure i will not exceed 10 CFR Part 100 dose guidelines or GDC-19 dose limits for control room operators.

Information obtained on iodine spiking will be used to assess the parameters associated with, spiking 3henomena. A reduction in frequency of isotopic analysis following power c1anges may be permissible, if justified by the data obtained.

Closing the main steam line isolation valves prevents the release of activity to the environs should the steam line rupture occur. The

surveillance requirements provide adequate assurance that excessive specific

i. activity levels in the reactor coolant will be detected in sufficient time to take corrective action.

l 3/4.4.6 PRES $URE/ TEMPERATURE LIMITS

, All components in the Reactor Coolant System are designed to withstand

! the effects of cyclic loads due to system temperature and pressure changes.

i These cyclic loads are introduced by normal load transients reactor trips.

and start-up and shutdown operations. The various categories of load cycles used for design purposes are provided in Section 4.2 of the FSAR. During BRUNSWICK - UNIT 1 B 3/4 4-3 Amendment No.

l I

ENCLOSURE 9 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 NRC DOCKET NOS. 50-325 AND 50-324 OPERATING LICENSE NOS. DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY TYPED TECHNICAL SPECIFICATION PAGES - UNIT 2 l

i REACTOR COOLANT SYSTEM 3/4.4.5 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.5 The specific activity of the reactor coolant shall be limited to: 1

a. less than or equal to 0.2 Ci/ gram DOSE EQUIVALENT I-131. and L

1 i

.b. less than or equal to 100/ E pCi/ gram.

APPLICABILITY: OPERATIONAL CONDITIONS 1. 2. 3. and 4.

ACTION:

a. In OPERATIONAL CONDITION 1. 2. and 3 with the specific activity of the reactor coolant:

1. Greater than 0.2 pC1/ gram DOSE EQUIVALENT I-131 but less than or equal to 3.0 pCi/ gram operation may continue for up I to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided that operation under these conditions shall not exceed 10 percent of the unit's total yearly operating time.

l The provisions of Specification 3.0.4 are not applicable.

l l

2. Greater than 0.2 pC1/ gram DOSE. EQUIVALENT I-131 for more than

! 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or greater than f 3.0 gCi/ gram. be in at least HOT SHUTDOWN with the main steam I line isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

i

! 3. Greater than 100/ 5 pC1/ gram, be in at least HOT SHUTDOWN with j the main steam line isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and i l

in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

! b. In OPERATIONAL CONDITION 1, 2. 3. or 4.

f

1. With the specific activity of the primary coolant greater than 0.2 pCi/ gram DOSE EQUIVALENT I-131 or greater than

~

100/ E gCi/ gram, perform the sampling and analysis requirements of Item 4b or Table 4.4.5-1 at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> until the specific activity of the primary coolant is restored to within its limits. In lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to i S)ecification 6.9.2 a Special Report that defines the results of I tie specific activity analyses and the time duration when the specific activity of the coolant exceeded 0.2 gCi/ gram DOSE EQUIVALENT I-131 together with the below additional information.

l

[- 4 i

BRUNSWICK - UNIT 2 3/4 4-10 Amendment No.

l

REACTOR COOLANT SYSTEM BASES The surveillance requirements provide adecuate assurance that concentrations in excess of the limits will be cetected in sufficient time to l take corrective action.

In order to reduce personnel radiation exposure, chemical decontamination of portions of the reactor coolant system may be performed during shutdown. During the chemical decontamination process. the injection ,

of chemical solvents may cause the reactor coolant system conductivity and l chloride measurements to increase above the limits. The solvents that are selected for use in performing the chemical decontamination process are selected and evaluated to ensure their chemical reactivity will not adversely impact components o, the structural integrity of the reactor coolant system.

Because decontamination activities are performed at temperatures significantly less than normal operating temperatures, the chemical reactivity of these solvents will not increase the likelihood of stress corrosion occurring nor affect those stress corrosion cracks that may already be present.

3/4.4.5 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the 2-hour thyroid and whole body doses resulting from a main steam line failure outside the containment during steady state operation will not exceed small fractions of the dose guidelines in 10CFR 100. Permitting operation to continue for limited time periods with higher specific activity levels accommodates short-term iodine spikes which may be associated with power level

! changes, and is based on the fact that a : team line failure during these short time periods is considerably less likely. Operation at the higher activity levels, therefore, is restricted to a small fraction of the unit's total operating time. The upper limit of coolant iodine concentration during short-term iodine spikes ensures that the thyriod dose from a steam li.ne failure will not exceed 10 CFR Part 100 dose guidelines or GDC-19 dose limits for control room operators.

Information obtained on iodine spiking will be used to assess the parameters associated with. spiking ahenomena. A reduction in frequency of ,

isotopic analysis following power c1anges may be permissible. if justified by (

the data obtained.

Closing the main steam line isolation valves prevents the release of activity to the environs should the steam line rupture occur. The i surveillance requirements provide adequate assurance that excessive specific activity levels in the reactor coolant will be detected in sufficient time to take corrective action.

3/4.4.6 PRESSURE / TEMPERATURE LitLI_LS All components in the Reactor Coolant System are designed to withstand the effects of cyclic loads due to system temperature and pressure changes.

l These cyclic loads are introduced by normal load transients, reactor trips, and start-up and shutdown operations. The various categories of load cycles used for design purposes are provided in Section 4.2 of the FSAR. During l

BRUNSWICK - UNIT 2 B 3/4 4-3 Amendment No.