ML20069J106

Proposed TS Re SGTS & Secondary Containment

ML20069J106
Person / Time
Site:	Monticello
Issue date:	06/08/1994
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20069J096	List: ML20069J092 ML20069J101 ML20069J106
References
NUDOCS 9406140184
Download: ML20069J106 (13)

Text

1 l

Exhibit B Monticello Nuclear Generating Plant License Amendment Recuest dated June 8. 1994 Proposed Changes Marked Up on Existing Technical Specification Pages .

Exhibit B consists of the existing Technical Specification pages with the proposed changes marked up on those pages. Existing pages affected by this change are listed below:

EATA 166 167 168 169 170 (No Changes, for information only) 188 l

l 1

1 i

9406140184 940608 PDR ADDCK 05000263 P PDR l

3.0 LIMITING CONDITIONS FOR OPERATION i.0 SURVEILLANCE REQUIREMENTS

c. Except for inerting and deinerting operations permitted in (b) above, all containment purging and venting above cold shutdown shall be via a 2-inch purge and veat valve bypass line and the Standby Cas Treatment System. Inerting and deinerting operations may be via the 18-inch purge and vent valves.(equipped with 40-degree limit stops) aligned to the Reactor Building plenum and vent.

6. If the specifications of 3.7. A cannot be met, the reactor shall be placed in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

B. Standby Cas Treatment System B. Standby Cas Treatment System

1. Two separate and independent standby 1. ^

.. 1 ::t :::: p:r :: th, ic.iti::: fr: .

gas treatment system circuits shall be ^: ::ntr:1 :::: c^^ f: (ila;) fl:,;

operable at all times when secondary th:: ugh 5:th ir: nit: :f th: t ene'-

containment integrity is. required, except as specified in sections gr tr n : t ry ter. C kASC 3.7.B.l.(a) and (b). 1 O n ce_ per mon % oPc'"4*-

a. After one of the. standby gas MA h [sn Ok OL treatment system circuits is made or found to be inoperable for any g g/ , g y y reason, reactor operation and fuel g I yde 3 o r 1lO c.o d.wsucat handling is permissible only during ggp the succeeding seven days, provided that.all active components in the hoes y)iO Oc bE 3 q hghrs other standby gas treatmeny sys' tem are operable. Within Whours follow-OfCJAgi^3-ing the 7 days, the reactor shall be placed in a condition for which the standby gas treatment system is not required in accordance with Specification 3.7.C.2.(a) through (d).

3.7/4.7 166 REV-127 2,'15,'91

n.

e 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIREMENTS

b. If both standby gas treatment C h"*3C- system circuits are not operable, 3 w rithin'*M-hours the reactor shall t/ O be placed in a condition for which the standby gas treatment system ,

is not required in accordance with Specification 3.7.C.2.(a) through (d). 2. Performance Requirement Tests

2. Performance Requirements a. At.least once per 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation; or once per. operating cycle,

a. Periodic Requirements but not to exceed 18 months, whichever occurs first; or following painting, (1) The results of the in-place fire, or chemical release in any vent-DOP tests at 3500 cfm (110%) ilation zone communicating with the on HEPA filters shall show s stem while'the system is operating

<1% DOP penetration,

~ t at could contaminate the HEPA filters C- "SC-or charcoal ebeorbeee, perform the 2_

(2) The results of in-place halo-genated hydrocarbon tests at following: g g 3500 cfm (i10%) on charcoal (1) In-place DOP test the HEPA filter banks shall show <1% penetra- banks.

, tion.

(2) In-place test the charcoal adsorber (3) The results of laboratory banks with halogenated hydrocarbon sample analysis shall. tracer.

ckysgC. N,carbt,_

show % methyl iodine re-moval efficiency when tested (3) Remove-one carbon test canister 1]g at 1-30^e, 9 5 % -R,44--

7 from the charcoal adsorber. Sub-30 (.,

rc,\divc, h tA=w ; &i-\7 ject this sample to a laboratory-analysis to verify methyl iodine removal efficiency.

3.7/4.7 167 REV 127 2/10/31 i

~

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIREMENTS

b. The system shall be shown to b. At least once per operating cycle. .but-be operable with: C,hos3y net t: : :::d 18 :: nth:, the following 2~

conditions shall be demonstrated for (1) Combined filter pressure each standby gas treatment system:

drop ~<6 inches water.

C' "'^00~ (1) Pressure drop across the combined (2) Inlet heater power output filters of each standby gas treat-l7 > 1skW.

~

R- I B ment system circuit shall be (3) Automatic initiation upon measured at 3500 cfm (110%) flow rate, C g"^60- receipt of following inputs:

(2) Operability of inlet heater at C3 y (bK) High drywell pressure, or nominal rated power shall be

s. verified.

(V) Reactor building ventilation plenum high radiation, or (3) Automatic initiation of each d standby gas treatment system (p) Refueling floor high radiation. circuit.

3. Post Maintenance Requirements 3. Post Maintenance Testing

a. After any maintenance or testing a. After any maintenance or testing that could affect the HEPA filter that could affect the leak tight or HEPA filter mounting frame integrity of the HEPA filters, leak tight integrity, the results perform in-place DOP tests on the -

of the in-place DOP tests at 3500 HEPA filters.

cfm ( 10%) on HEPA filters shall show <1% DOP penetration.

~ b. After any maintenance or testing that

b. After any maintenance or testing could affect the leak tight integrity of the charcoal adsorber banks, per-that could affect the charcoal form halogenated hydrocarbon tests adsorber leak tight integrity, the on the charcoal adsorbers, results of in-place halogenated hydrocarbon . tests at 3500 cfm (110%) on charcoal adsorber banks shall show <1% penetration.

i Low bv_ko P MW 3.7/4.7 [-(odLc.v LW c\,oc

[6E && ' 't' S '

o. .

..3

-

• b , ,

)

3.0 LIMITING CONDITIONS FOR OPERATION

. 4.0 SURVEILIANCE REQUIREMENTS C. Secondary Containment C. Secondary Containment

1. Except as specified in 3.7.C.2 and 1. Secondary containment surveillance shall I 3.7.C.3, Secondary Containment Integrity be performed as indicated below; shall be maintained during all modes of plant operation. a. Secondary containment. capability to

2. Secondary Containment. Integrity is not maintain at least a 1/4 inch of water required when all of the following con- vacuum under calm wind (4--+ u < 5 mph) '

ditions are satisfied: conditions with a filter train flow rate of <4,000 scfm, shall be dem- a

a. The reactor is subcritical and Cg"^% onstrated at each refueling outage Specification 3.3.A is met. prior to refuelingA. Verification 7 that eacn automaclY damper' actuates

b. to its isolatio osition shall The reactor water temperature is below 212*.

be performed;ad' ch refueling outage,

- (, Dam 4 Af ter maintenance, repair or replace-:

c. No activity is being performed which ment work is performed on the damper or can reduce the shutdown margin below its associated actuator, control circuit,

• or power circuit. ~i that specified in Specification 3.3.A

d. The fuel cask or irradiated fuel is not being moved within the reactor building.

M cM e A A Cu^ b 0^b do WOg a y,g

3. With an inoperable secondary contain- - durI Q Of 1. kE. Edin 3 3 ment isolation damper, restore _the inoperable 4.Q 4g d d 3 ig -l o be.

damper to operable status or isolate the affected duct by use. of. a . closed damper or cor g d ko cA( $4s Wi nd-- i blind flange within eight hours. (condikion5,

4. If Specifications 3.7.C.1 through 3.7.C.3 cannot be met, initiate a normal orderly shutdown and have the C hvNof, reactor in the Cold Shutdown condition 3

within 4de hours. . Alterations of the 48 -

3.7/4.7 169 REV 120 12/20/'?O e- r -. e.- m we! ta r em e *'-ea' me =eBH _r_.mv1 - p _-1. s _ _ _ - _ _ - - - . - _

e ., ..

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS reactor core, operations with a potential for reducing the shutdown

• margin below that specified in specification 3.3.A, and handling of irradiated fuel or the fuel cask in the secondary containment are to be immediately suspended if secondary containment integrity is not main-tained.

D. Primary Containment Automatic Isolation Valves D. Primary Containment Automatic Isolation Valves

1. During reactor power operating conditions, 1. The primary containment automatic isolation valve all Primary Containment automatic isolation surveillance shall be performed as follows:

valves and all primary system instrument line flow check valves shall be operable except a. At least once per operating cycle the as specified in 3.7.D.2. operable isolation valves that are power operated and automatically initiated shall be tested for simulated automatic initiation and closure times,

b. At least once per operating cycle the primary system instrument line flow check valves shall be tested for proper operation. -

c. All normally open power-operated isolation valves shall be tested pursuant to Specification 4.15.B. Main Steam isolation valves shall be tested.(one at a time) with the reactor power less than 75% of rated.

3.7/4.7 170 REV 127 2/15/91

4 + .

! Bases Continued:

B. Standby Cas Treatment System, and C. Secondary Containment' Initiating reactor building isolation and operation of the standby gas treatment system to maintain the design negative pressure within the secondary containment provides~an adequate test of the reactor building isolation valves and the standby gas treatment system. Periodic testing gives sufficient confidence of reactor building integrity and' standby gas. treatment system operational capability.

The frequency of tests and. sample analysis are necessary to show that the HEPA filters and b charcoal adsorbers cari perform as evaluated. ' Standby' gas. treatment system inplace testin= 1989 l N @

procedures will be established utilizing applicable sections of ANSI N510-1^Z%ndard-as a procedural guideline only. ";ici . h.;t;r; in th; :t;;i , ;;; t;;;- at ;s t: ::::

. ' Y 7, .. ..

w..< p. 7 e +'

s'-drzt . If painting, fire,;or. chemical release occurs .I such that the HEPA filter or charcoal adsorber could become contaminated from the fumes, ggc, chemicals, or foreign materials, the same tests and sample. analysis should be performed as required for operational use. Replacement adsorbent should-be qualified according'to'the Ib guidelines of Regulatory Guide l.52 Revision 2/ (J ; 1??f). The charcoal adsorber efficiency 1

Mofc.h test procedures will allow for the removal of eme. representative sample -- *- 9; tThe sample 19'T B will be at least two inches in diameter and a ldhgth equal to the thickness of the bed. If.

the iodine removal efficiency test results are unacceptable, all adsorbent in the-system will be replaced. High efficiency particulate filters are installed before and after the charcoal filters to prevent clogging of the carbon adsorbers and to. minimize potential release of particulates to the environment. An efficiency of 994 is adequate to retain particulates that bNJ may be released to the reactor building following an accident. ~This will_be demonstrated by 'g O Og inplace testing.with DOP as the. testing medium. Any HEPA filters found defective will'be.

replaced with filte s qualified pursuant to regulatory guide position C.3.d_of Regulatory 41$ gg Guide 1.52 Revisio / (l=;,1??6) . Once per operating; cycle demonstration of HEPA filter-W yg pressure drop, operability of inlet heaters at rated power, ' automatic- initiation of each standby gas treatment system circuit, and' leakage tests after maintenance or' testing which could affect leakage, is necessary to assure system performance capability. ~

74 3, o"c_. , 9 5 '/o. rdedWc heid dy fea w A W G MS- W .

gg .}- Q i c.S k f(\CM'\ od kO tNC 'b b i o d i d.C_, i'C.W\O\/M C'- IC ACy b #- - C 4.7 BASES 188 REV 52 1/^/01

l- 1 l

l .

1 Exhibit C j

! l l 1 Monticello Nuclear Generating Plant License Amendment Reauest dated June 8. 1994 Revised Technical Specification Pages l

2 l Exhibit C consists of the Technical Specification pages with the proposed

( changes incorporated. Existing pages affected by this change are listed I i below:

' l l

ZaT&

166' 167 168 I 169 188 1

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIREMENTS

c. Except for inerting and deinerting operations permitted in (b) above, all containment purging and venting above cold shutdown shall be via a 2-inch purge and vent valve bypass line and the Standby Gas Treatment System. Inerting and deinerting operations may be via the 18-inch purge and vent valves (equipped with 40-degree limit stops) aligned to the Reactor Building plenum and vent.

6. If the specifications of 3.7.A cannot be met, the reactor shall be placed in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

B. Standby Gas Treatment System B. Standby. Gas Treatment System

1. Two separate and independent standby 1. Once per month, operate each train of gas treatment system circuits shall be the standby gas treatment system for operable at all times when secondary 210 continuous hours with the inline containment integrity is required, except as heaters operating.

specified_in section 3.7.B.l.(a) and (b).

a. After on of the standby gas treatment system circuits is made or found to be inoperable for any reason, reactor

. operation and fuel handling is permissible only during the succeeding seven days, provided that all active components in the other standby gas treatment system are operable. Within 48 I hours following the 7 days, the reactor shall be placed in a condition for which the standby gas treatment system is not required in accordance with Specification 3.7.C.2.(a) through (d).

3.7/4.7 166 REV

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIREMENTS

b. If both standby gas treatment system

circuits are not operable, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> the reactor shall be placed in a condition for which the standby gas treatment system is not required in accordance with Specification 3.7.C.2.(a) through (d).

2. Performance Requirements 2. Performance Requirement Tests

a. Periodic Requirements a. At least once per 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operations; or once per operating cycle, (1) The results of the in-place but not to exceed 18 months, whichever DOP tests at 3500 cfm ( 10%) occurs first; or following painting, on HEPA filters shall show fire, or chemical release in any vent-

$1% DOP penetration. ilation zone communicating with the system while the system is operating (2) The results of in-place halo- that could contaminate the HEPA filters genated hydrocarbon tests at or charcoal adsorbers, perform the l 3500 cfm (i10%) on charcoal following:

banks shall show $1% penetra-tion. (1) In-place DOP test the HEPA filter banks.

(3) The results of laboratory carbon sample analysis shall (2) In-place test the charcoal adsorber show 294% methly iodine re- banks with halogenated hydrocarbon I moval efficiency when tested tracer, at 30*C, 95% relative humidity.

! (3) Remove one carbon test canister from the-charcoal adsorber. Sub-ject this sample to a laboratory analysis to verify methyl iodine removal efficiency.

3.7/4.7 167 REV

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS

b. The system shall be shown to be b. At least once per operating cycle, the l operable with: following conditions shall be demonstrated for each standby gas (1) Combined filter pressure treatment system:

drop $6 inches water.

(1) Pressure drop across the combined (2) Inlet heater power output filters of each standby gas treat-218kW. ment system circuit shall be l

measured.at 3500 cfm (i10%) flow (3) Automatic initiation upon rate.

receipt of following inputs:

(2) Operability of inlet heater at (a) Low Low Reactor Water Level, nominal rated power shall be or verified.

(b) High drywell pressure, or (3) Automatic initiation of each standby gas treatment system (c) Reactor building ventilation circuit.

plenum high radiation, or

3. Post Maintenance Testing (d) Refueling floor high radiation

a. After any maintenance or testing

3. Post Maintenance Requirements that could affect the leak tight integrity of the HEPA filters,

a. After any maintenance or testing perform in-place DOP tests on the that could affect the HEPA filter HEPA filters.

or HEPA filter mounting frame leak tight integrity, the re.ults b. After any maintenance or testing that of the in-place DOP tests at P' 00 could affect the leak tight integrity cfm (110%) on HEPA filters s' of the charcoal adsorber banks, per-show $1% DOP penetration, form halogenated hydrocarbon tests on the charcoal adsorbers.

b. After any maintenance or testing that could affect the charcoal adsorber leak tight integrity, the results of in-place haloger. aced hydrocarbon tests at 3500 cfm (110%) on charcoal adsorber banks shall show $1% penetration.

3.7/4.7 168 REV

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIREMENTS C. Secondary Containment C. Secondary Containment

1. Except as specified in 3.7.C.2 and 1. Secondary containment surveillance shall 3.7.C.3, Secondary Containment Integrity be performed as indicated below:

shall be maintained during all modes of plant operation. a. Secondary containment capability to maintain at least a 1/4 inch of water

2. Secondary Containment Integrity is not vacuum under calm wing (u < 5 mph) l required when all of the following conditions with a filter train flow conditions are satisfied: rate of $4,000 scfm, shall be demonstrated at each refueling outage

a. The reactor is subcritical and prior to refueling. If calm wind Specification 3.3.A is met. conditions do not exist during this testing, the test data is to be

b. The reactor water temperature is corrected to calm wind conditions.

below 212*F.

b. Verification that each automatic

c. No activity is being performed which damper actuates to its isolation can reduce the shutdown margin below position shall be performed:

that specified in Specification 3.3.A (1) Each refueling outage,

d. The fuel cask or irradiated fuel is not being moved within the reactor (2) After maintenance, repair or building. replacement work is performed on the damper or its associated

3. With an inoperable secondary containment actuator, control circuit, or isolation damper, restore the inoperable power circuit.

damper to operable status or isolate the affected duct by use of a closed damper or blind flange within eight hours.

4. If Specifications 3.7.C.1 through 3.7.C.3 cannot be met, initiate a normal orderly shutdown and have the reactor in the Cold Shutdown condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Alterations of the 3.7/4.7 169 Rev

Bases Continued:

i B. Standby Gas Treatment System, and C. Secondary Containment Initiating reactor building isolation and operation of the standby gas treatment system to maintain the design negative pressure within the secondary containment provides.an adequate test of the reactor building isolation valves and the standby gas treatment system. Periodic testing gives sufficient confidence of reactor building integrity and standby gas treatment system operational capability.

. The frequency of tests and sample analysis are necessary to show that the HEPA filters and charcoal

adsorbers can perform as evaluated. Standby gas treatment system inplace testing procedures will be established utilizing applicable sections of ANSI N510-1989 standard as a procedural guideline only. If l painting, fire, or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated from the fumes, chemicals, or foreign materials, the same tests and sample analysis should be i performed as required for. operational use. Replacement adsorbent should be qualified according to the -

guidelines of Regulatory Guide 1.52 Revision 2 (March 1978). The charcoal adsorber efficiency test  !

procedures will allow for the removal of a representative sample. The 30*C, 95% relactive humidity test per l

ASTM D3803-1989 is the test method to establish the mythel iodide removal efficiency of the adsorbent. The sample will be at least two inches in-diameter and a length equal to the thickness of the bed. If the iodine removal efficiency test results are unacceptable, all adsorbent in the system will be replaced. High efficiency particulate filters are installed before and after the charcoal-filters to prevent clogging of the carbon adsorbers and to minimize potential release of particulates to the environment. An efficiency of 99% is adequate to retain particulates that may be released to the reactor building following an accident.

This will be demonstrated by inplace testing with DOP as the testing medium. Any.HEPA filters found ,

defective will be replaced with filters' qualified pursuant to' regulatory guide position C.3.d of Regulatory Guide 1.52 Revision 2 (March 1978). Once per operating cycle demonstration of HEPA filter pressure _ drop, g operability of inlet heaters at rated power, automatic initiation of each standby- gas treatment- system circuit, and leakage tests after maintenance or testing which could affect leakage, is necessary to assure system performance capability.

4.7 BASES 188 REV

_. _ _ - - _ - - _ _ _ _ ____ .- ._ - - . - - . .