ML19312E349

Draft Safety Evaluation Supporting Proposed Amend 29 to License DPR-36 to Add Air Filter Tech Specs 3.22 & 4.11. Modified Tech Specs Encl

ML19312E349
Person / Time
Site:	Maine Yankee
Issue date:	05/29/1980
From:	BROOKHAVEN NATIONAL LABORATORY
To:
Shared Package
ML19312E347	List: ML19312E346 ML19312E349
References
NUDOCS 8006040268
Download: ML19312E349 (25)

Text

e DRAFT SAFETY EVALUATION BY BATTELLE-PACIFIC NORTHWEST LABORATORY FOR THE OFFICE OF NUCLEAR REGULATION Supporting Proposed Change No. 29 to License No. DPR-36 fiaine Yankee Atomic Power Company - Maine Yankee Plant Docket No. 50-309 INTRODUCTION By letter dated January 27, 1977 and revised version, March 19, 1980, the Maine Yankee Atomic Power Company proposed to amend its operating license DPR-36 for the Maine Yankee Plant by submitting Proposed Change No. 29.

The proposed amendment added specification 3.22 to establish Limiting Conditions for Operation and 4.11 to establish Surveillance Requirements, relative to installed filter systems to the itaine Yankee Technical Specifications.

The proposed amendment also revises pages 3.13-2 and 4.2-4 to the Technical Specifications referencing the added specifications and deleting the current surveillance requirement from Table 4.2-2.

The table of contents for the Technical Specifications is also revised to reflect the addition of Specification 3.22 and 4.11.

We have reviewed and evaluated these proposed changes and additions.

Our evaluation was based on the standard Technical Specification for engineered safety feature (ESF) ventilation filter systems for operating nuclear reactors and with Positions C.5 (in-place testing criteria) and C.6 (laboratory testing criteria for activated charcoal) of Regulatory Guide 1.52, (Revision 2), " Design, Testing and Maintenance Criteria for Atmospheric Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Potter Plants."

EVALUATION The licensee proposed to add Section 3.22, Installed Ventilation and Filter Systems, to the existing technical specifications.

This specification applies to the operability of the containment hydrogen purge system, control room ventilation and spent fuel pool venti.lation systems.

Specification A on the containment hydrogen purge system requires " Hot Shutdown" within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The standard Technical l

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DRAFT Specifications require hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and the proposed change should be altered from 12 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Specification B on control room ventilation requires, "With one control room ventilation system inoperable, restore the system to operable status within 14 days or be in Cold Shutdown within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />."

In order to conform to the standard Technical Specification, the preceding sentence should be, "With one control room ventilation system inoperable, restore the system to operable status within 7 days or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />."

With the above changes the proposed specification, Section 3.22, is consistent with the standard Technical Specification and would be acceptable.

The licensee proposed to add Section 4.11, Ventilation Filter System Surveillance Testing to specify the surveillance requirements necessary to demonstrate the operability of the containment hydrogen purge system, the control room ventilation system and the spent fuel ventilation system.

The proposed technical specifications are not entirely consistent with the standard Technical Specification for ESF ventilation filter system and Positions C.5 and C.6 of Regulatory Guide 1.52.

The following changes or additions are suggested to complete the technical specifications with the changes underlined.

4.11.B.2 At least each refueling interval or at least once oer 18 months and followina painting.

4.ll.B.2.b Verifying within 31 days after removal that the results of laboratory carbon sample analysis...

4. l l. C.1 The Spent Fuel Pool Ventilation System shall be demonstrated operable at least once ner month by initiating system flow throuoh the HEPA filter and charcoal absorber train for at least 15 minutes.

When irradiated fuel...

2

DRAFT 4.ll.C.2.b Verifyina within 31 days after removal that the results of laboratory carbon samole analysis...

! lith the above changes the proposed technical specification is consistent with the model Technical Specification for ESF ventilation filter systems and Positions C.5 and C.6 of Regulatory Guide 1.52, except that the specifications for testing air heaters were deleted.

Heaters for humidity control on the filter systems are not installed at the fiaine Yankee Atomic Power Plant since design parameters do not require them at this facility.

Our evaluation of this filter system was based on the assumption that the relative humidity would not be controlled.

Therefore, we agree with the licensee that there is no need for air heaters in this filter system.

Accordingly, we conclude that the deletion of the tech-nical specifications for testing air heaters is acceptable.

ENVIRONfiENTAL CONSIDERATION l

We have deter

..aot the proposed amendment does not authorize a change in effluent types, an increase in total amounts of effluents or an increase in power level and will not result in any significant environ-mental impact.

Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the 1

standpoint of environmental impact and pursuant to 10 CFR 51.5(d)(4), that an environmental imoact appraisal need not be prepared in connection with the issuance of this amendment.

CONCLUSION Based on the above evaluation, we determined that the proposed changes and additions to the Technical Specification for the fiaine Yankee Power Plant meet the requirements of the model Technical Specification for engineered safety feature ventilation filter systems for operating nuclear reactors and of Positions C.5 and C.6 in Regulatory Guide 1.52, (Revision 2).

Accordingly, we conclude that the proposed amendment, as submitted and modified, is acceptable.

3

DRAFT

~

We also conclude that:

1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety maroin, the amendment does not involve a significant hazards consideration; 2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; and 3) sucn activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety to the public.

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REVISED 2-13-80 by Maine Yankee Plant Attachment A

~~

DRAFT 3.22 INSTALLED VENTILATION AND FILTER SYSTEMS Applicability:

Applies to the operating status of the plant installed ventilation and filter systems.

Objective:

To define the operating status of the installed ventilation and filter systems required for plant operation.

Specification:

A.

The containment hydrogen purge system shall be operable whenever the reactor is critical. With the containment-hydrogen purge system inoperable, restore the hydrogen purge system to operable status within 30 days or be in Hot Shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

I B.

One train of control room ventilation shall be operable whenever minimum safeguards are required.

Two trains of control room ventilation shall be operable whenever the reactor is critical.

With one control room ventilation system inoperable, restore the system to operable status within 7 days or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Note:

Each control room ventilation system consists of one recirculation system @ 4700 cfm and one breathing air supply system at 40 cfm.

C.

Spent Fuel Pool Ventilation Requirements 1.

When irradiated fuel which has decayed less than 60 days is in the spent fuel pool, the spent fuel ventila-tion system shall be operating and discharging through a HEPA and charcoal adsorber filter train during either:

a.

Fuel movement within the spent fuel pool, or b.

Crane operation with loads over the spent fuel pool.

2.

With C.1 abova not satisfied, suspend all operations involving movement of fuel within the spent fuel pool or crane operation with loads over the spent fuel pool.

Basis:

The operability of the equipment and systems required for the detection and control of hydrogen gas insures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions.

The operability of the control room ventilation system ensures that the control room will remain habitable for operations personnel during and following all credible accident conditions.

REVISED 2-13-80 by Mai e nk l

ttachment A The operability of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.

This limitation is consistent with the requirements of General Design Criteria 19 of Appendix "A", 10 CFR 50.

The limitations on the storage pool ventilation system ensure that all radioactive material released from the design basis fuel drop accident 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 a/sumptions of the accident analyses.

It has been shown that after a 60-day decay period the offsite doses from a fuel drop accident with no filtration are significantly less than for the design basis accident with fil tra tion.

REVISED 2-13-80 by fiaine Yankee Plant Attachment A Page Three DRAFT 4.11 VENTILATION FILTER SYSTEli SURVEILLANCE TESTING Applicability:

Applies to the containment hydrogen purge system, the control room ventilation system,and the spent fuel pool ventilation system.

Objective:

To specify the surveillance requirements necessary to demonstrate the operability of the above specification and filter systems.

Specification:

A.

Containment Hydrogen Purge System 1.

The hydrogen purge system shall be demonstrated operable at least once per month by initiating system flow through the HEPA filter and charcoal adsorber train for at least 15 minutes and verifying that the purge system operates by observing flow indication on the system flowmeter.

2.

The hydrogen purge system discharges via the safety related fuel building deep bed charcoal filter bank.

Surveillance testing of these filters is accomplished via section C.2 of this specification.

B.

Control Room Ventilation System 1.

Each control room ventilation system shall be demonstrated operable at least once per month on a staggered test basis by initiating flow through the HEPA filter and charcoal adsorber train for at least 15 minutes verifying train operability.

2.

At least each refueling interval or at least once per l

18 months and following painting, fire or chemical release in any ventilation zone connunicating with the system, while the system is operating, that could contaminate the HEPA filters or charcoal adsorbers, the filter system shall be demonstrated operable by verifying that:

a.

The results of the in-place cold DOP and halogenated hydrocarbon tests at design flows on HEPA and charcoal filter banks shall show 299% D0P removal and 299% halogenated hydrocarbon removal.

b.

Verifying within 31 dyas after removal that the l

results of laboratory carbon sample analysis shall show 295% radioactive methyl iodide removal.

(25 C, 70% R.H.)

c.

Recirculation filter system flow rate is 4700 cfm 20 percent during system operation.

REVISED 2-13-80 by Maine Yankee Plant Attachment A Page Four tendI.j.

Y R

i d.

Breathing air supply system flow rate is 40 cfm 20 percent during system operation.

3.

Following maintenance or replacement 'ctivities, only those components which may have been adversely affected by the activity need be tested.

Specifically:

a.

Cold 00P testing shall be performed after each complete or partial replacement of the HEPA filter bank.

b.

Halogenated hydrocarbon testing shall be performed after each complete or partial replacement of the charcoal filter bank.

In addition, the sample analysis of Specification 4.11.B.2.b shall be performed after every 720 hrs.

of system operation.

c.

00P and halogenated hydrocarbon test shall be performed following any significant modification to the filter housing that could have an adverse affect on the filter efficiency.

d.

An air distribution test demonstrating uniformity within 20% across the HEPA filters and charcoal adserbers shall be performed if the filter housing is modified such that air distribution could be adversely affected.

C.

Spent Fuel Pool Ventilation System 1.

The Spent Fuel Pool Ventilation System shall be demonstrated operable at least once per month by initiating system flow through the HEPA filter and charcoal adsorber train for at least 15 minutes.

When irradiated fuel which has decayed less than 60 days is in the spent fuel pool, the spent fuel pool ventilation system shall be verified to be operating 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 initiation of and at least once per shift during either fuel movement within the spent fuel pool or crane operation with loads over the spent fuel pool.

Note: Operating shall be defined as: At least one purge fan operating, and system aligned to provide flow through the filter train from the spent fuel building.

REVISED 2-13-80 by Maine Yankee Plant Attachment A Paga Five DRAFT 2.

At least each refueling interval and following painting, fire cr chemical release in any ventilation zone communicating with the system, while the system is operating, that could contaminate the HEPA filters or charcoal adsorbers, the filter system shall be demonstrated operable by verifying that:

a.

The results of the in-place cold D0P and halogenated hydrocarbon tests at design flows on HEPA and charcoal filter banks shall show 299% DOP removal and 299% halogenated hydrocarbon removal.

b.

Verifying within 31 days after removal that the l

results of laboratory carbon sample analysis show 299% radioactive methyl iodide removal.

(22 C, 70% R.H.)

c.

Filter system flow rate is 23,000 CFM 20 percent during system operation.

3.

Following maintenance or replacement activities, only those components which may have been adversely affected by the activity need be tested.

Specifically:

a.

Cold D0P testing shall be perfonned after each complete or partial replacement of the HEPA filter bank.

b.

Halogenated hydrocarbon testing shall be performed after each complete or partial replacement of the charcoal filter bank.

In addition, the sample analysis of Specification 4.ll.C.2.b shall be performed after every 1500 hrs. of system operation.

c.

D0P and halogenated hydrocarbon test shall be per-formed following any significant modification to the filter housing that could have an adverse affect on the filter efficiency.

d.

An air distribution test demonstrating uniformity within 20% across the HEPA filters and charcoal adsorbers shall be performed if the filter housing is modified such that air distribution could be adversely affected.

Basis:

To insure that the H2 purge, control room and spent fuel pool filter systems will be effective in removing radioactive contaminates-from their respective air streams, these systems will be tested periodically to meet the intent of ANSI N510-1975.

REVZSED 2-13-80 by Maine Yankee Plant Attachment A Page Six In specification 4.ll.C.1 the reference to a 60 day decay period is appropriate because calculations have shown that af ter a 60 day decay the off-site doses from a fuel drop accident with no filtration are significantly less than those from the design basis accident with filtration.

In specification 4.ll.C.2.b, the 299% radioactive methyl iodide removal requirement is necessary because 95% removal credit was taken for the H2 purge contribution to the LOCA dose.

In specification 4.ll.C.3.b, the increase in the testing interval from 720 hrs. to 1500 hrs. is appropriate because of the incorporation of both a 4 inch bed of activated impregnated charcoal bed and a 1" guard bed of activated charcoal.

I j

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2-DRAFT ATTAC'rCEST 3 TO PROPOSD CHA';GE No. 29 SUPPLFliENT #1 Revised page 3.13-2 and 4.2-4 to the. Maine Yankee Technical Specifications, and revised Table of Contents p:ges 1 a..d 2 Note:

The revision to page 4.2-4 deletes existing page 4.2-5.

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6.

Direct connunication between persennel in the control roc and at the refueling s:aticn shall be cper:ble whenever changes in core gecce:ry are taking place.

3.

~f any of the conditiens in Specification A. are not. net, all refueling operations shall cease 1 ediately; work shall be initia:ed to satisfy the recuired conditions, and no operations tha: may increase the reactivity of tne core scall.ce Cade.

C.

For spent fuel pool ventilation require ents, reference Specifica:ica 3.22.

D.

?rior to initial core loading and prior to each refueling, a co:plete check cut, including a 1 cad test, shall be conducted en fuel handling cranes that will be used to handle spen: f u el as s e:b lie s.

E.

A nininua of 23 feet of water abcve the tcp of -he core shall be raintained whenever spent fuel is being handled.

F.

Irradiated fuel shall not be handled for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> af ter reac:or.shutdcun.

Iesis:

The ecuip ent and general procedures to be utili ea during refueling are discussed in the FSAR.

Detailed instructions, the abcVe specifica:icas and the desi;r cf the fuel handling equiprent incorporating built-in intericchs and safe;uards systecs provide assurance that no incident could occur during the refueling operations that wculd result in a hazard to public heal:h and saf ety.

(1)

Whenever changes are not being cade in core geenetry, cne flux r.cnitor is sufficient.

This perrits maintenance of the instru:enta:ica.

Centinucus conitoring of radiatica levels and neu:ren flux provides inmediate indica: ion of an unsafe cenditien.

The residual heat renoval z-.icu

_,s used to recove core decav. neat and

=aintain a unifor: bcron concentration.

The shutdcun =argin as indicated will keep the core sub-stan:ially subcritical, even if the highes worth CEA's cere inadvertently withdraum frc the core wi:hout ccapensating boron ac...c1:1cn.

Periedic checks of refueling water beren cencent' ation insure

.he proper shutdown cargin.

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opera c: 0:. any 1Cpencing unsa:e Cenc1:1cn ce*eC:eQ IrC

ne Cain Cent!Cl beard indica crs during fuel =cVerent.

i 3.13-2

Tabic 4.2-2 b

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u-Trecuencies for Ecuirrents Tests J ",

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2 Test Frecuency 1.

Cen:!cl 7'=-a--

Asse:blies Drep Tires of all full-length Each refueling (C a.,s C u.,s

.nter'.a 2.

Centrol Elarent Assa blies Partial Movement of all CEA's Every two weeks when (mini =um of 6")

the reactor is criti 3.

Pressurizer Safety Valves Set Point One valve each refueling interval 4.

Mnin Steam Safe:y Valves Set Point 2 valves per stea:

generator, each refueling in:erval 5.

Eefueling Syste: Inter-Functioning Prior to refueling

,A c c.es operations 6.

Fire ?; ps Functioning Quarterly 7.

Prin:ry Syste Leakage Evaluate Daily **

3.

Diesel Fuel Supply

' Fuel Inventory Weekly 9.

Turbine S:cy, Governor, Functioning Monthly when the

?.eheat and Intercept turbine is oper-valves ating 10.

L.P. Turbine Rotor Visual, Magnetic Particle.

One rotor each 4 inspe::icn or Liquid ?cnetrant years 11.

? s:-acciden contain-Calibra t e Upen installa:ic cen: vant syste: Hyd:cgen and within ene centh deteC Cr of startup frC: each refueling shu:dewn

• • k'henev4r the reaC Or COClan syste3 is at or ahCVe OOeratin~ Oressure.

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5 Defini:icns Page 1.1 Fuel Storage 1.1-1 1.2 Site Description 1.2-1 1.3 Reactor 1.3-1 1.4 Contain=ent 1.4-1 2.0 Safety Limits and Maxi u: Safety Settings 2.1 Licitin; Safe:y Set:ings Reacecr Protection Syste:

2.1-1 2.2 Sefe:y Limits - Reac:or Core 2.2-1 2.3 Safety Licits - Reactor Ceclant Syste= ?ressure 2.3-1 3.0.

Limiting Ccn'diticas for Operation 3.1 Incore Instru en:ation 3.1-1 3.2 Reactor Coelan: Syste: Ac:ivity 3.2-1 3.3 Reactor Coolan: Syste Cperatienal Cc=penents 3.3-1 3.4 Cc:bined Heat-up, Cooldews and Press-Terp. Limits 3.4-1 3.5 Che ical and Velure Centrol Sys:e 3.5-1 3.6 Core Cooling and Cenrain=en: Spray Systers 3.6-1 3.7 Mini =ue Water *leluca and Boron Concentration 3.7-1 3.8 Reactor Core Energy Renoval 3.8-1 3.9 Operational Saf e:y Ins:ru=entation and Control Syste=s 3.9-1 3.10 CIA Group and Peuer Distribu:icn Lisits 3.10-1 3.11 Centain=ent 3.11-1 3.12 Station Service Power 3.12-1 3.13 Refueling Operatiens 3.13-1 3.14 Pri=ary Syste: Leakage 3.14-1 3.15 Reac:ivity Anc:alics 3.15-1 3.15 Radioactive Licuid '.'as:e Release 3.16-1 3.17 Radioactive Gasecus Waste Release 3.17-1 3.19 Che:istry 3.18-1 3.19 Saf ety Inj ectica Valving 3.19-1 3.20 Shock Suppressers (Snubbers) 3.20-1 3.21 Stea: Generators 3.21-1 3.22 Ventila:ica and Filter Systens 3.22-1 4.0 Surveillance Require ents 4.0-1 4.1 Ins:re:ents:1cn and Con:rol 4.1-1

4.2 Zeuipmen

and Sa:pling Tests 4.2-1 4.3 Reactor Coolan: Syste: Leak Tests 4.3-1 4.4 Contain=en: Tes:ing 4.4-1 e

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able of Centen s 4.5 Incr;ency Fewer Syste: Periodic Testing 4.5-1 4.6 Periodic Testing 4.6-1 4.7 Reactor Coolan Sys:ca Surveillance Testing 4.7-1 4.E Operaticnal Invirc. ental Monitoring 4.8-1 L9 Sheck Suppressor (Snubber) Surveillance 4.9-1 4.10 5:ea-Genera :: Tube Surveillance 4.10-1 4.11 Ven:ilatica and Fil:er System surveillance Testing 4.11-1 5.0 Administrative Centrols 5.1 Crganization.

5.0-1 5.1-1

5. 2-Review and Audi:

5.2-1 5.3 A.O. Actica 5.3-1 5.4 Safe y Lini: Ac-icn 5.4-1 5.5

?lan: C; era-in; ?recedures 5.5-1 5.6 Plant Operatin; ?.eccrds 5.6-1 5.7 Plan Cpera-ing Escuipetents 5.7-1 5.8 Radioicgical Procedures 5.8-1 l

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Wm.1 REVISED 2-13-80 by Maino Yankta Plant AttcchmInt A

~

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Page Ons 3.22 INSTALLED VESTILATION' AND FILTER SYSTD!S Aoplicabilitv:

Applies to the operating status of the plant installed ventilation and filter systems.

Objective:

To define the operating status of the installed ventilation and filter systems required for plant operation.

Specification:

A.

The containment hydrogen purge syste= shall be operable whenever the reactor is critical.

With the containment-hydrogen purge system inoperable, restore the hydrogen purge system to operable status within 30 days or be in Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

B.

One train of control room ventilation shall be operable whenever mini =um safeguards are required.

Two trains of control room ventilation shall be operable whenever the reactor is critical.

With one control room ventilation system inoperable, restore the system to operable status within 14 days or be in Cold Shutdown within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Note:

Lich control room ventilation system consists of one recirculation system @ 4700 efs and one breathing air supply system at 40 cfm.

C.

Spent Fuel Fool Ventilation Require =ents 1.

When irradiated fuel which has decayed less than 60 days is in the spent fuel pool, the spent fuel'ventila-tion system shall be operating and discharging through a HEPA and charcoal adsorber filter train during either:

Fuel move =ent within the spent fuel pool, or a.

b.

Crane operation with loads over the spent fuel pool.

2.

With C.1 above. net satisfied, suspend all operations involving move =ent of fuel within the spent fuel pool or crane operation with loads over the spent fuel pool.

Basis:

The operability of the equipment and systems required for the detection and control of hydrogen gas insures that this equipment will be available to =aintain the hydrogen concentration within containment below its fla==able limit during post-LOCA conditions.

The operability of the control room ventilation system ensures that the control room will remain habitable for operations personnel during and following all credible accident conditions.

The oper-ability of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control roo.m to 5 rem or less whole body, or its equivalent.

This li=itation is consistent with the requirenents of General Design Criteria 19 of Appendix "A",10 CFR 50.

3.22-1

i REVISED 2-13-80 by Maina Ycnksa Plcnc

}

Attachment A

):

Pags Twa t t%

The 11=itations.on the storage pool ventilation system ensure that all radioactive material released from the design basis fuel drop accident will'oe filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. The operability of this system ud the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.

It has been.shown that after a 60-day decay period the offsite doses from a fuel drop accident with no filtration are significantly less than for the design basis accident with filtration.

4 3.22-2

.R5 VISED 2-13-80 by.P.ina Yanksg f1cnt,

AttachmInt A iL i

Pags Thrsa 4.11 VENTILATION FILTER SYSTEM SURVEII. LANCE TESTING Apolicability:

Applies to the contaic=ent hydrogen purge syste=, the control room ventilation system, and the spent fuel pool ventilation system.

Objective:

To specify the surseillance requirements necessary to de=onstrate the operability of the above specification and filter systems.

Soecification:

A.

Containment Hydrogen Purge System 1.

The hydrogen purge system shall be demonstrated operable at least once per =onth by initiating system flow through the EEPA filter and charcoal adsorber train for at least 15 =inutes and verifying that the purge system operates by observing flow indication on the system flowmeter.

2.

The hydrogen purge syste= discharges via the safety related fuel building deep bed charcoal filter bank.

Surveillance testing of these filters is accomplished via sec~ tion C.2 of this specification.

B.- Control Room Ventilation System 1.

Each control room ventilation system shall be demonstrated operable at least once per month on a reaggered test basis by initiating flow through the HEPA filter and charcoal adsorber train for at least 15 minutes verifying train operatility.

2.

At least each refueling interval and following painting, fire or chemical release in any ventilation zone co=municating with the system, while the system is operating, that could conta", ate the HEPA filters or charcoal adsorbers, the filter system shall be de=onstrated operable by

)

verifying that:

The results of the in-place cold DOP and halogenated a.

hydrocarbon tests at design flows on HEPA and charcoal filter banks shall show >_99% DOP re= oval and b.99%

halogenated hydrocarbon removal.

b.

The results of laboratory carbon sample analysis shall show 2.95% radioactive methyl iodide re= oval.

0 (25 C, 70% R.H.)

c.

Recirculation filter system flow rate is 4700 cfm I 20 percent during system operation.

d.

Breathing air supply system flow rate is 40 cfm I 20 percent during system operation.

e%(

. REVISED 2-13-80 by Mains Yankaa Pltnt Attechm:nt A r#.5 Page Four 3.

Following =aintenance or replacement activities, only those components which may have been adversely affected by the activity need be tested.

Specifically:

a.

Cold DOP testing shall be perforned after each complete or partial replacement of the EEPA filter bank.

b. 'Halogenated hydrocarbon testing shall be performed after each complete or partial replacement of the charcoal filter bank.

In addition, the sample analysis of Specification 4.ll.3.2.b shall be performed after every 720 hrs.

of system operation.

c.

DOP.and halogenated hydrocarbon test shall be performed following any significant modification to the filter housing that cou?' have an adverse affect on the filter efficiency.

d.

An air distribution test demonstrating unifor=1ty within

• 20% across the HEPA filters and charcoal adsorbers shall be performed if the filter housing is modified such thr t air distribution could be adversely affected.

C.

Spent Fuel Fool Ventilation System 1.

When irradiated fuel which has decayed less than 60 days is in the spent fuel pool, the spent fuel pool ventilation system shall be verified to be operating 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 initiation of and at least once per shift during either fuel movement within the spent fuel pool or crane operation with loads over the spent fuel pool.

Note:

Operating shall be defined as:

At least one purge fan operating, and system aligned to provide flow through the filter train from the spent fuel building.

l 2.

At least each refueling interval and following

-painting, fire or chemical release in any ventilation zone co==unicating with the system, while the system is operating, that could contaminate the HEPA filters or charcoal adsorbers, the filter system shall be demonstrated operable by verifying that:

The results of the in-place cold DOP and halogenated a.

hydrocarbon tests at design flows on HEPA and charcoal filter banks shall show 299% DOP re= oval and 199%

halogenated hydrocarbon re= oval.

Attachmtat A REVIS D 2-13-80 by Mains Ycnksa Plcutp,..

C

Pega Fiva tse b.

The results of laboratory carbon sample analysis shov 299% radioactive methyl iodide removal.

(25 C, 70% R.H.)

I 20 percent Filter system flow rate is 23,000 CFM c.

during system operation.

3.

Following maintenance or replacement activities, only those. components which may have been adversely affected by the activity need be tested.

Specifically:

Cold DOP testing shall be performed af ter each a.

complete or partial replacement of the HEPA

. filter bank.

b.

Halogenated hydrocarbon testing shall be performed

.after each complete or partial replacement of the charcoal filter bank.

In addition, the sa=ple analysis of Specification 4.ll.C.2.b shall be performed af ter every 1500 hrs. of system operation.

c.

DOP and halogenated hydrocarbon test shall be per-formed following any significant modification to the filter housing that could have an adverse affect on the filter efficiency.

d.

An air distribution test de=onstrating uniformity within 20% across the HEPA filters and charcoal adsorters shall be performed if the filter housing is modified such that air distribution could be adversely affected.

Basis:

To insure that the H2 purge, control room and spent fuel pool filter systems will be effective in removing radioactive contaminates from their respective air streams, these systems will be tested periodically to meet the intent of ANSI N510-1975.

In specification 4.ll.C.1 the reference to a 60 day decay j

period is appropriate because calculations have shown that l

after a 60 day decay the off-site doses from a fuel drop accident with no filtration are significantly less than those l

from the design basis accident with filtration.

In. specification 4.ll.C.2.b, the 399% radioactive methyl iodide removal requirement is necessary because 95% removal credit was taken for the H2 purge contribution to the LOCA dose.

In specification 4.ll.C.3.b, the increase in the testing

' interval from 720 hrs. to 1500 hrs. is appropriate because of the incorporation of both a 4 inch bed of activated imprer;nated charcoal bed and a 1" guard bed of activated Echarcsal.

ATTAC' RENT 3 TO PROPOSED CH.GGE NO. 29 SUPPLDIEST #1 Revised page 3.13-2 and 4.2-4 to the >!aine Yankee Technical Specifications, and revised Table of Contents p:ges 1 and 2 Note:

The revision to page 4.2-4 deletes existing page 4.2-5.

O e

-a.

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Direct cc :enica:icn be:veen persennel in the control rocs and at the refueling s:atien shall be cperable whenever changes in core gecretry are taking place.

3.

If any of the conditiens in Specification A. are not.tet, all refueling operations shall cease i=cediately; work shall be initiated to satisfy the required conditions, and no operations that may increase the reactivity of the core shall be =ade.

C.

For spent fuel pool ventilation require ents, reference Specification 3.22.

~

D.

?rior to initial core loading and prior to each refueling, a cceplete check out, including a lead test, shall be conducted on fuel handling cranes that will be used to handle spent fuel asse=blies.

E.

A inimum of 23 feet of water abcVe the tcp of the core shall be maintained whenever spen: fuel is being handicd.

F.

Irradiated fuel shall not be handled for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after reactor.shutdcun.

Iasir:

The equiptent and general procedures to be utilized during refueling are discussed in the FSAR.

Detailed instructions, the ibeve specifica:icas and the desi;n cf :he fuel handling equiptent incorporating built-in interlecks and safeguards syste s provide assurance that no incident eculd occur during the refueling operations that would resui: in a hazard to public health and safety.

(1) b'henever changes are not being cade in core geo=etry, cne flux cenitor is sufficient.

This per=its naintenance of the instruzentation.

Con:inuous monitoring of radiation levels and neutron flux provides i==ediate indication of an unsafe cendition.

The residual heat renoval flow is used to re=cve core decay heat and maintain a uniforn boron concentration.

The s':

Cown cargin as indica:ed will keep the core sub-stan:ially suberitical, even if the highese worth CEA's were inad.'ertently withdrawn from :he core without ec=pensating boron addition.

Periodic checks of refueling water berca cencentration insure the c. roc.er shutdown =argin.

Cc==unicatica recuire=ents allcu the c:n:rol rec: opera:or to infor the refueling statica opera:cr of any 1 pending unsafe cenditica detected frc= the

=ain control board indica: ors during fuel :ove ent.

e 4

3.'13-2

Table 4.2-2 Minit - Frecuencies for Ecui:nents Tests Test Frecuenev 1.

Cen:rel Elenen: Asse:blies Orep Tires of all full-length Each refueling (CT.A' s )

CEA's interval 2.

Cc trol Ela:ent Assa blies Partial Movenent cf all CEA's Every two veeks when

( ini un of 6")

the reae:or is critics 3.

Pressurizar Safety Valves Set Point one valve each refueling interval 4.

Main S:ea: Safe:y Valves Set Point 2 valves per ster generator, each refueling interval 3.

Refueling Sys:e In:er-Functioning Prior to refueling

.ss operations 6.

Tire Purps Functioning Quarterly 7.

?ritary Syste Leakage Evaluate Daily **

~

8.

Die.sel Fuel Supply Fuel Inventory Weekly 9.

Turbine S:cp, Governor, Functioning Menthly when the

?.eheat and Intercept turbine is oper-valves ating 10.

L.P. Turbine Rote:

Visual, Magnetic Par:icle one rotor each 4 Inspection or Liquid Penetrant years 11.

?cs:-accident contain-Calibrate Upen installatic:

=en: vent systen Hydrogen and within ene centh detec:or of-startup f c each refueling shu: dews

• • Whenever the reactor coolant systen is at or above opera:ing pressure.

b G

4.2-4 e

TECHNICAL SPICIFICATIONS

..o Table cf Centen:s Definitiens Pace 1.1 yuel Storege 1.1-1 1.2 Site Descriptien 1.2-1 1.3 Reactor 1.3-1 1.4 Centain=en:

1.4-1 t

2.0 Safety Limits and Mani:c: Safety Settings 2.1 Li=iting Safety Settings Reactor Pro:ec:fon Sys:e=

2.1-1 2.2 Safety Limits - Reac:or Core 2.2-1 2.3 Safety L1=its - Reactor Coolan: Syste Pressure 2.3-1 3.0 L1=iting Cenditions for Ope:ation ac 3.1 Incore Instru en:ation 3.1-1 3.2 Reactor Ccelan: Sys:e= Ac:ivity 3.2-1 3.3 Reactor Ceolan: Sys:e Opera:icnal Cc:penen:s 3.3-1 3.4 Cc-bined Hea:-up, Cooldeve and Press-Te:p. Limits 3.4-1 3.5 Chemical and Vclure Centrci tysta:

3.5-1 3.6 Core Cooling and Ccnrainmen: Spray Sys:ess 3.6-1

3.7 Minieu

Water Veluce and 3eron Cencentration 3.7-1 3.8 Reac:or Core Energy Re cval 3.8-1 3.9 Operational Saf e:y Instrumen:atica and Control Sys: ens 3.9-1 3.10 CEA Group and ?over Dis:ribution Lizits 3.10-1 3.11 Con:ainment 3.11-1 3.12 5:a:1on Se vice Power 3.12-1 3.13 Refueling Opera:1cns 3.13-1 3.14 Pri=ary Syste: Latkage 3.14-1 3.15 Reac:1vity Anc:alics 3.15-1 3.16 Radioactive Licuid L'asce Release 3.16-1 3.17 Radioactive Gasecus Waste Release 3.17-1 l

3.19 Che:is:ry 3.18-1 3.19 Saf ety Inj ection Valving 3.19-1 3.20 Shock Suppressors (Snubbers) 3.20-1 3.21 S:ea: Generators 3.21-1 3.22 Ventila: ion and yilter Sys: ens 3.22-1 4.0 Surveillance Require:en:s 4.0-1 4.1 Instruner.ts:icn and Con:rol 4.1-1

4.2 Ecuipnet

and Sa:pling Tests 4.2-1 4.3 Reacto*: Coolan-Sys:e Leak Tests 4.3-1

4.4 Centainmen

Tes:ing 4.4-1 S

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TEC'-;'UC/.?. SPECI?ICATIONS Tchle of Conten:s 2-l 4.5 I: rgency ? cue: Syste: ?criodie Testins 4.5-1 4.6 Periodic Testi:S 4.6-1 4.7 Eeactor Coolan: Sys:en Surveillance Testing 4.7-1 j

4.8 0;eraticnal Invircnnents1 Moni:oring 4.8-1 4.9 Sheck Suppresser (Snubber) Surveillance 4.9-1 4.13 Stea. Senerater Tube Surveillance 4.10-1 4.11 Ven:ilation and 711:e System Surveillance Testing 4.11-1 5.0 Ad=inistrative centrols 5.0-1 5.1-1

~

5.1 C:gani:stion.

5. 2-Revie.: and Audit 5.2-1 e,

,n

-.s n.v.

nc:.on 5,3-1 1

5.4 Sadety Limi: A :ien

5. 4-1 5.5 Flan: C; era:in; ?::cedures 5.5-1 5.6 Plant Cperating Eeccrds 5.6-1 t

5.7 Plant operating Eecei;erents 5.7-1 5.8 Radiological Precedures 5.8-1 1

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