ML20082N871

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Proposed Tech Specs Re SBGTS & Secondary Containment
ML20082N871
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 04/20/1995
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20082N859 List:
References
NUDOCS 9504250423
Download: ML20082N871 (13)
v • d • e


Text

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Exhibit B {

Monticello Nuclear Generating Plant j i

Revision 1 to License Amendment Reauest dated June 8.1994 t

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: .;

1 P_R92 166 '

167 .

168 l 169 170 (No Changes, for information only) i 188 I

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t 9504250423 950420 DR .ADOCK 05000263

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3.0 LIMITING CONDITIONS FOR OPERATION i.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 Cas Treatment System B. Standby Gas Treatment System

1. Two separate and independent standby 1. ^

..t 12 :t n: per :: nth, initict: fr: ..

gas treatment system circuits shall be th: :: tr:1 :::: 35^^ :f 'i1^.; fic,w operable at all times when secondary th; u gh 5:th cir it: :f th: steney containment integrity is required, g: tr r' rnt cyrt r. g 3g' except as specified in sections 1

3.7.B.1.(a) and (b). O n ce_ per mon % oP'O

a. After one of the standby gas MO Y * '

treatraent system circuits is made or found to be inoperable for any g4 gg ao 4 gg-\ gpi-ggke korJ 2IO c_ o d.w cal

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reason, reactor operation and fuel handling is permissible only during i the succeeding seven days, provided hours y)IO Oe *^C-that.all active components in the other standby gas treatment system h M c.r b are operable. Within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> follow- O f C/ A4I^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-

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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIREMENTS

b. If both standby gas treatment system circuits are not operable, '

within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> the reactor shall 1; 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 -

1

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
a. -Periodic Requirements operation; or once per operating cycle, 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 (i10%) 11ation zone communicating with the on HEPA filters shall show s stem while the system is operating

<14 DOP penetration,

- t at could contaminate the HEPA filters C k%D ^IVL or charcoal cir:rt;;;, perform the -2_-

(2) The results of in-place halo-genated hydrocarbon tests at following:

dSorY)tfL 3500 cfm (ilot) 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.

c,bsatysgil. CfhI,,Sarba show bet methyl iodine re- .

moval efficiency when tested i

(3) Remove one carbon t9st canister ijpg at 13&Se, 95% 4 ,H- from the charcoal adsorber. Sub-7 t c \divc. htAmidik/ ject this sample to a laboratory l

30 (_ analysis to verify methyl iodine removal efficiency. j i

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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS

b. The system shall be shown to b. At least once per operating cycle, but be operable with:

not to exceed 18 months, the following conditions shall be demonstrated for (1) Combined filter pressure each standby gas treatment system:

drop <6 inches water.

gg3c 7; e. (1) Pressure drop across the combined (2) ter power output filters of each standby gas treat-l7 c. . T he. *> ysb hltlBbe, s ka '^ ment system circuit shall be

+o be_opa,bl J measured at 3500 cfm (ilot) flow Automatic initiation upon rate.

gg receipt of following inputs: ;4 f ina.

Ae (2) Operability of inlee heater at 6 > (bJ) High drywell pressure, or nominal rated power shall be

s. verified.

(W) Reactor building ventilation C_. M Icas+ . o.4u r>v o P u ^ b.^3 'YC le-s C bny-plenum high radiation, or d M sfutomatic standby gas initiation treatmentofsystem each 2-(p) Refueling floor high radiation. circuit $bh be k 4ons+4ke2,

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 (i10%) on HEPA filters shall show <lt DOP penetration.

'- b. After any maintenance or testing that could affect the leak tight integrity

b. After any maintenance or testing 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 (ilot) on charcoal adsorber banks shall show <lt penetration.

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3.7/4.7 b 1-c vc2 l OC E M '/^ M

L 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

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. The reactor is suberitical and b"^ % onstrated at each refueling outage Specification 3.3.A is met. prior to refuelingA . Verification

~7 tnat eacn automatic damper actuates to its isolation position shall

b. The reactor water temperature is be performed edPE ch refueling outage.-

below 212*. (i)amejhfter 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, that specified in Specification 3.3. A
d. The fuel cask or irradiated fuel is not being moved within the reactor building.

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3. With an inoperable secondary contain-ment isolation damper, restore the inoperable 4Q gd dd s i s -4 o b y.

damper to operable status or isolate the LM vn co f gi rd -k r> W i a d-affected duct by use.of a closed damper or blind flange within eight hours. (C.o n d M ,o A 5 ..

4. If Specifications 3.7.C.1 through 3.7.C.3 cannot be met, initiate a normal orderly shutdown and hava the .

CMM, C reactor in the Cold Shutdown condition within & hours. Alterations of the L 7 36 3.7/4.7 169 REV 120 12/20/90

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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 i

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 -

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Bases Continued! IO "~' M D N b ab 5 5 AM c. 61e rs W'le.cNo rbC-k*N f o.-- - M i

Secondary Containment Tn4. , gL; M @ ,.f h4e2 MY ab I97 1 Initiating reactor building isolation and operation of the standby gas treatment system to g 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 7 testing gives sufficient confidence of reactor building integrity and standby gas treatment system operational capability, y The frequency of tests and. sample analysis are necessary to show that the HEPA filters and Y charcoal adsorbers can perform as evaluated. Standby gas treatment system inplace testing g$89 procedures will be established utilizing applicable sections of ANSI N510-l*7", % ndard l -

as a procedural p,.... u guideline only. Re dund;.. h;;;;;; i; th; ;;;.d*,, g;; :;.; r;;; ;7; ::

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If painting, fire, or chemical release occurs .I such that the HEPA filter or charcoal adsorber could become contaminated from the fumes,

& r, chemicals, or foreign materials, the same tests and sample analysis should be performed as required for operational use.

'9b Replacement adsorbent should be qualified according to the l guidelines of Regulatory Guide 1.52 Revision 27 (J.-- 1976) . The charcoal adsorber efficiency Mofc.h test procedures will allow for the removal of ene. representative sample ---*- , . tThe sample I l 'f 7 6 will be at least two inches in diameter and a 14hgth equal to the thickness of the bed. If l

thereplaced.

be iodine removal efficiency test results are unacceptable, all adsorbent in the system will 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 may be released to the reactor building following an accident. This will be demonstrated by MNJ th',

O Ng inplace testing with DOP as the testing medium. Any HEPA filters found defective will be replaced with filtegs qualified pursuant to regulatory guide position C.3.d of Regulatory

</15 g g g Guide 1.52 Revision'/ (Jun: '??6). Once per operating cycle demonstration of HEPA filter 197B Pressure drop, operability of .ia&et heaters at rated power, automatic initiation of each standby gas treatment system ci SIdti and leakage tests after maintenance or testing which could affect leakage, is necessary to assure system performance capability.

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4.7 BASES

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Exhibit C Monticello Nuclear Generating Plant Revision 1 to License Amendment Reauest dated June 8.1994 Revised Technical Specification Pages Exhibit C consists of the Technical Specification pages with the proposed changes incorporated. Existing pages affected by this change are listed below:

Egge 166 167 168 169 188 1

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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 inc:a purge and vent valves (equipped witi. 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 le 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 one 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 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> 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 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-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 (110%) 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 ( 10%) on charcoal following:

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

(3) The results of laborato n carbon sample analysis shall (2) In-place test the charcoal adsorber el '94% : methyl iodine re- banks with halogenated hydrocarbon mo... 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 SURVEILIANCE REQUIREMENTS

b. The system shall be shown to be b. At least once per operating cycle, but operable with: not to exceed 18 months, the following conditions shall be demonstrated for each (1) Combined filter pressure standby gas treatment system:

drop $6 inches water.

(1) Pressure drop across the combined (2) Inline heater power output filters of each standby gas treat-218kW. ment system circuit shall be measured at 3500 cfm (110%) flow l c. The system shall be shown to be rate.

operable with automatic initiation upon receipt of the following inputs: (2) Operability of inline heater at i nominal rated power shall be l (a) Low Low Reactor Water Level, verified.

or

c. At least once per operating cycle, (b) High drywell pressure, or automatic initiation of each standby gas treatment system circuit shall be (c) Reactor building ventilation demonstrated.

plenum high radiation, or (d) Refueling floor high radiation

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 (i10%) on HEPA filters shall show $1% DOP penetration. b. After any maintenance or testing that could affect the leak tight integrity

b. After any maintenance or testing 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 (i10%) on charcoal adsorber banks shall show $1% penstration. 168 3.7/4.7 REV m_--..____ - _ _ _ _ _ _ - _ _m -m. .-_ - + ++4e -

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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 wind (u < 5 mph) I required when all of the following conditions with a filter train flow conditions are satisfied: rate of $4,000 sefa, shall be demonstrated at each refueling outage
a. The reactor is suberitical 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 l
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 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Alterations of the l

3.7/4.7 169 Rev

4 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. Secondary Containment-  ;

capability test data obtained under non calm wind conditions is to be extrapolated to calm wind conditions using information provided in " Summary Technical Report to the United States Atomic Energy Commission, '

Directorate of Licensing, on Secondary Containment Leak Rate Test," submitted by letter dated July. 23, 1973.

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 I 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

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 -l  ;

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

ASTM D 3803-89 is the test method to establish the mythel iodine 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. .lf 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 i the carbon adsorbers and to minimize potential release of particulates to the environment. An efficiency of 991 is adequate to retain particulates that may be released to the reactor building followingian 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, -l ,

operability of inline heaters at rated power, automatic initiation of each standby; gas treatment system g circuit, and leakage tests after maintenance or testing which could affec_t leakage, is necessary to assure system performance capability.

4.7 BASES 188 REV

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