ML18054B553: Difference between revisions

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{{#Wiki_filter:SIT FILL AND DRAIN I SAMPL*E LINEUP * -0"1Nl 00
{{#Wiki_filter:SIT FILL AND DRAIN I SAMPL*E LINEUP SIRWT
::uo -1:1!. llJ . l>O 00 0-0 gg CUI T-82 SINK T-82 SIRWT *(JI-**;-* / I I I / i --.:___J CV-3069 a OTHER 2 SIT F&D I PCV VALVES  
    * -0"1Nl 00 -*-~
.... -itb .... -Vl * ..........
::uo
_-r-OIAROINO PUMPS ... ,
            -1:1!.
OC0390-0005-NL02 ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES April 11, 1990 2 Pages TABLE 4.2.1 Frequencies for Sampling 1. Reacior Coolant Samples 2. Reactor Coolant Boron 3. SIRW Tank Water Sample i Test Gross Activity mination Gross Gamma by Fission Product Monitor Isotopic analysis for dose equivalent concentration  
llJ .
*Radio chemical for E determination Isotopic analysis for iodine, including I-131, 133, 135 Chemistry (Cl and 02) Chemistry (Fl) Boron Concentration Boron Concentration
l>O             T-82                    T-82 00
: 4. Concentrated Boron Concentration Boric Acid Tanks 5. SI Tanks Boron Concentration
        ~8
* Frequency 3 Times/7 days with* a maximum of 72 hours tween samples (T avg greater than 500°F). Continuous when T avg is greater thant 500°F(l).
                                ._~SAMPLE SINK 0-0 gg
1/14 days during power operation 1/6 months (2) a) Once/4 hours, whenever dose equivalent I-131 exceeds 1.0 µCI/gram, and b) One sample between 2 and 6 hours ing a thermal power change exceeding 15% of rated thermal power within a one hour period. 3 times/7 days with a maximum of 72 hours between samples (T avg greater than 210°F). Once/30 days and ing modifications or repair to the primary coolant system involving welding. Twice/Week Monthly Monthly Monthly For T-82A, for the remainder of Cycle 8 but not after September 30, 1990, following a PCS boron change greater than 80 ppm below the equivalent hot full power value, a sample will be taken within one hour. 4-14 FSAR Section Reference None None None None None None None
      -08~
* 6.1.2 I I I I I Amendment No. 7<<, tti, OC0390-0005-NL02 3.3 EMERGENCY CORE COOLING SYSTEM Applicability Applies to the operating status of the emergency core cooling system. Objective To assure operability of equipment required to remove decay heat from the core in either emergency or normal shutdown situations.
zru~
Specifications Safety Injection and Shutdown Cooling Systems 3.3.1 The reactor shall not be made critical, except for low-temperature physics tests, unless all of the following conditions are met:
CUI
* a. The SIRW tank contains not less than 250,000 gallons of water with a boron concentration of at least 1720 ppm but not more than 2000 ppm at a temperature not less than 40&deg;F. b. All four Safety Injection tanks are operable and pressurized to at least 200 psig with a tank liquid level of at least 186 inches (55.5%) and a maximum level of 198 inches (59%) with a boron *. concentration of at least 1720 ppm but not more than 2000 ppm. I c. One low-pressure Safety Injection pump is operable on each bus. d. One high-pressure Safety Injection pump is operable on each bus. e. Both shutdown heat exchangers and both component cooling heat exchangers are operable.
  ~ ~* *(JI-**;-
: f. Piping and valves shall be operable to provide two flow paths from the SIRW tank to the primary cooling system. g. All valves, piping and interlocks associated with the above components and required to function during accident conditions are operable.
* /
: h. The Low-Pressure Safety Injection Flow Control Valve CV-3006 shall be opened and disabled (by isolating the air supply) to prevent spurious closure. i. The Safety Injection bottle motor-operated isolation valves shall be opened with the electric power supply to the valve motor disconnected.
I I
: j. The Safety Injection miniflow valves CV-3027 and 3056 shall be opened with HS-3027 and 3056 positions to maintain them open. For the remainder of Cycle 8, but not after September 30, 1990, Safety I Injection Tank T-82A is required to have a boron concentration greater than I or equal to the equivalent hot full power primary coolant system boron I concentration, but not to exceed 2000 ppm. I 3-29 Amendment No. 7<<,
I CV-3069
OC0390-0005-NL02 OC0390-0005-NL02 ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 MARKED UP TECHNICAL SPECIFICATION PAGES April 11, 1990 2 Pages
              /     i
. ' ' l* Reactor Coolant Samples*
        --.:___J a
* 2. Reactor Coolant. Boron 3. SIRW Tank Water *sample 4. Concentrated**
                                  ~:_:/
Boric Acid Tanks TABLE 4.2.1 Minimum Frequencies for. Sampling Tests.' Test* Gross Activity mination Gross Gamma. by Fission . Product Monitor Isotopic analysis for dose equivalent . I-131 concentration Radio chemical for E determination Isotopic analysis for iodine, including I-131, 133, 135 Chemistry-(Cl and 02) Chemistry (Fl) Boron Concentration Boron Concentration Boron Concentration Frequency 3 Times/7 days with a maximum of 72 hours tween samples (T avg greater than 500&deg;F). Continuous when T'avg is greater thant 500&deg;F(l).
OTHER 2 SIT
1/14 days during power operation*
                                                    ....
1/6 months (2) -a) Once/4 hours, whenever dose equivalent I-131 exceeds 1.0 &#xb5;CI/gram, and b) One sauiple between .2 and 6 hours ing a thermal power. change exceeding 15% of rated thermal power within a one hour period. 3 times/7 days with a maximum of 72 hours between samples (T avg greater than 210&deg;F). Once/30 days and ing modifications or repair to the primary coolant system involving welding. Twice/Week Monthly Monthly .:.;*11 . '.'; I FSAR .r""-* .,, , Section --:: $ *Reference None None .: None None Norte None None 5. SI Tanks Boron* Concentration Monthly 6. 1. 2 I * *' .p.c:n -li.t.. . I . S b.J1.;J .30/ /q?D,1 JJc: .t/ow1rio .t!t-pr1"'11'1t:v1'1 j Po1WJ c/JPn')c..e_
F&D I PCV VALVES PC~......i-------------- -itb. . -Vl *.........._-r-PC~--------------1---Vl~ll-.I OIAROINO PUMPS
Pf' :;i q U/ll/. -1. ---1---:*
                                                        ...,
I * -ul . _..,,A )op)-Amendment No. Z0. 11 ** 11. p{!_ ./ e.VI TF-1 'l'1  
 
* ' March 25, 1988 TSP0987-0155-NL04   
ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES April 11, 1990 2 Pages OC0390-0005-NL02
. .J "''**** :.:[ k 3.3 EMERGENCY CORE COOLING SYSTEM . '.: . . _ Applicability , . Applies, co. the operacing status of the emergency core cool*ing system.
 
Objective To ci.ssu*ra*
                          ~            TABLE 4.2.1 M~um    Frequencies for Sampling FSAR Section Test                      Frequency          Reference
operability of equipment required:
: 1. Reacior Coolant   Gross Activity Deter-    3 Times/7 days with* a      None Samples            mination                  maximum of 72 hours be-tween samples (T avg greater than 500&deg;F).
to* remove decay heat from
Gross Gamma by Fission   Continuous when T avg is    None Product Monitor           greater thant 500&deg;F(l).
* the core in either emergency or normal shutdown Specifications*
Isotopic analysis         1/14 days during power      None for dose equivalent       operation I~l31 concentration i
Safety Injection and Shutdown Cooling System& 3. 3. l The reactor shall not be made cr.1tical except for low-temperature physics tests, unless all of the* following conditions are.met: a. The SIRW tank contains not less than* 250,000 gallons of water with a boron concentration of at least 1720 ppm but not more than 2000 ppm. at a temperature not less than_ 40&deg;r. . b. All four Safety Injection tanks are operable and pressuriZed
                      *Radio chemical for       1/6 months (2)              None E determination Isotopic analysis         a) Once/4 hours, whenever for iodine, including       dose equivalent I-131 I-131, 133, 135             exceeds 1.0 &#xb5;CI/gram, and b) One sample between 2 and 6 hours follow-ing a thermal power change exceeding 15%
* least 200 psig a tank liquid level of at least 186 inches .-;: (55.5%) and a maximum. level of 198 inches (59%) with a boron _* J
of rated thermal power within a one hour period.
* concentration of at least 1720 ppm but not more than 2000 ppm *. f * . j c. One. low-pressure Safety Injection pump is operable.
Chemistry (Cl and 02)    3 times/7 days with a maximum of 72 hours between samples (T avg greater than 210&deg;F).
on each bus. d. One high-pressure Safety Injection pump is operable on.each bus. e. Both shutdown heat* exchangers and both component cooling heat are operable.
Chemistry (Fl)           Once/30 days and follow-ing modifications or repair to the primary coolant system involving welding.
f.* Piping and shall be operable to provide two flow paths from the SIRW tank to the primary cooling system. g. All valves,. pip&#xb5;ig _and interlocks associated with the-above components and required to function during accident conditions are operable.
: 2. Reactor Coolant    Boron Concentration      Twice/Week                  None Boron
: h. The Low-Pressure Safety Injection Plow* Control Valve CV-3006 shall .be opened and disabled (by isolating the air supply) to prevent spurioua closure. * ' . i. The Safety Injection bottle isolation valves shall be opened with the electric power supply to the valve motor disconnected.
: 3. SIRW Tank Water    Boron Concentration      Monthly                      None Sample
: j. The Safety Injection miniflow valves CV-3027 and 3056 shall be opened with HS-3027 and 3056 positions to maintain them open. -*
: 4. Concentrated      Boron Concentration      Monthly                      None Boric Acid Tanks
d V\ a.8-g,1 b JI r>'IO\ a&#xa2;T".a-i b.vJ f *1GJfo.1*
: 5. SI Tanks          Boron Concentration      Monthly                      6.1.2
S'a<f?"T'1  
* I
\&deg;'""'):::.
*For  T-82A, for the remainder of Cycle 8 but not after                                  I September 30, 1990, following a PCS boron change greater                               I than 80 ppm below the equivalent hot full power value,                                  I a sample will be taken within one hour.                                                 I 4-14 Amendment No. l~. 7<<, tti, OC0390-0005-NL02
1-1?.2.l'i  
 
,.s-l--"'i'.S"''..:.""d -ro 3-29 . Amendment No. 7i, 101_ , . . February 10, 1987 . _ : .:h * {J . * *
3.3        EMERGENCY CORE COOLING SYSTEM Applicability Applies to the operating status of the emergency core cooling system.
* a... b C...:...V, ..
Objective To assure operability of equipment required to remove decay heat from the core in either emergency or normal shutdown situations.
D o-., e 't}'-'e l l."o o1 <f"tJJJ pow-lA, p>--1hYlt:t.114 s-11..?}'.
Specifications Safety Injection and Shutdown Cooling Systems 3.3.1      The reactor shall not be made critical, except for low-temperature physics tests, unless all of the following conditions are met:
b ; --TSP1285-03S4;..NL04 . &deg;' C/Y\ 1 """'/ b vT /l'\OT -* -1J}}
: a. The SIRW tank contains not less than 250,000 gallons of water with a boron concentration of at least 1720 ppm but not more than 2000 ppm at a temperature not less than 40&deg;F.
: b. All four Safety Injection tanks are operable and pressurized to at least 200 psig with a tank liquid level of at least 186 inches (55.5%) and a maximum level of 198 inches (59%) with a boron *.
concentration of at least 1720 ppm but not more than 2000 ppm.           I
: c. One low-pressure Safety Injection pump is operable on each bus.
: d. One high-pressure Safety Injection pump is operable on each bus.
: e. Both shutdown heat exchangers and both component cooling heat exchangers are operable.
: f. Piping and valves shall be operable to provide two flow paths from the SIRW tank to the primary cooling system.
: g. All valves, piping and interlocks associated with the above components and required to function during accident conditions are operable.
: h. The Low-Pressure Safety Injection Flow Control Valve CV-3006 shall be opened and disabled (by isolating the air supply) to prevent spurious closure.
: i. The Safety Injection bottle motor-operated isolation valves shall be opened with the electric power supply to the valve motor disconnected.
: j. The Safety Injection miniflow valves CV-3027 and 3056 shall be opened with HS-3027 and 3056 positions to maintain them open.
*For the remainder of Cycle 8, but not after September 30, 1990, Safety             I Injection Tank T-82A is required to have a boron concentration greater than         I or equal to the equivalent hot full power primary coolant system boron             I concentration, but not to exceed 2000 ppm.                                         I 3-29                   Amendment No. 7<<, t~t.
OC0390-0005-NL02
 
ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 MARKED UP TECHNICAL SPECIFICATION PAGES April 11, 1990 2 Pages OC0390-0005-NL02
 
'
  .'
TABLE 4.2.1 Minimum Frequencies for. Sampling Tests.'                                                    .:.;*1
                                                                                                                                      .   '.';
                                                                                                                            .r""-* .,, <~*~
FSAR                    ,
Section                -- :: $
Test*                               Frequency            *Reference l*      Reactor Coolant            Gross Activity Deter-            3 Times/7 days with a                None Samples*
* mination                        maximum of 72 hours be-tween samples (T avg greater than 500&deg;F).
Gross Gamma. by Fission . Continuous when T'avg is                   None                          .:
Product Monitor                greater thant 500&deg;F(l).
Isotopic analysis                1/14 days during power               None for dose equivalent            operation*
                                      . I-131 concentration Radio chemical for              1/6 months (2) -                     None E determination Isotopic analysis              a) Once/4 hours, whenever for iodine, including                  dose equivalent I-131 I-131, 133, 135                        exceeds 1.0 &#xb5;CI/gram, and b) One sauiple between
                                                                              .2 and 6 hours follow-ing a thermal power.
change exceeding 15%
of rated thermal power within a one hour period.
Chemistry- (Cl and 02)          3 times/7 days with a maximum of 72 hours between samples (T avg greater than 210&deg;F).
Chemistry (Fl)                  Once/30 days and follow-ing modifications or repair to the primary coolant system involving welding.
: 2.      Reactor Coolant.          Boron Concentration            Twice/Week                           Norte Boron
: 3.      SIRW Tank Water            Boron Concentration            Monthly                               None
        *sample
: 4.     Concentrated**             Boron Concentration            Monthly                              None Boric Acid Tanks
: 6. 1. 2 ~ I
* 5.
        *'. S SI Tanks e..pT~ b.J1.;J Boron* Concentration
                                        .30/ /q?D,1      JJc: .t/ow1rio Monthly For--T-~,:J.A 1 .p.c:n -li.t.. ~e,,,;;~4e~~/~ ~,,, bvT~~-r 4j'r~
                                                                          .t!t-   pr1"'11'1t:v1'1 c.oo/C;rl/..S:~sT~
                                                                                                                      . I j
Po1WJ        c/JPn')c..e_ ~C)..12t>J41 c/h~4~f              Pf'       :;i q Sa-n/71~ U/ll/.             -
: 1. ---1---:* I         * - ul . _..,,A   )op)-                           Amendment No. Z0. 11** 11.
p{!_ ./ O/~ e.VI TF-1           'l'1 ..,.,~        * '                       March 25, 1988 TSP0987-0155-NL04
 
:.:[ k::**-~
    -~
. .J   "''****
J  * ~-
3.3         EMERGENCY CORE COOLING SYSTEM
                                                                                                                              ~: . '.: .
                            . _ Applicability ,
                                      *;*.~--**:-
                              . Applies, co. the operacing status of the emergency core cool*ing system.
                                          ~--N Objective To ci.ssu*ra* operability of equipment required: to* remove decay heat from
* the core in either emergency or normal shutdown s~tuations.
Specifications*
Safety Injection and Shutdown Cooling System&
: 3. 3. l     The reactor shall not be made cr.1tical ~ except for low-temperature physics tests, unless all of the* following conditions are.met:
: a.         The SIRW tank contains not less than* 250,000 gallons of water with a boron concentration of at least 1720 ppm but not more than 2000 ppm. at a temperature not less than_ 40&deg;r.                 .
: b.         All four Safety Injection tanks are operable and pressuriZed to~at
* least 200 psig wit~ a tank liquid level of at least 186 inches .-;:
(55.5%) and a maximum. level of 198 inches (59%) with a boron                             _*
concentration of at least 1720 ppm but not more than 2000 ppm *.f *                           .j
: c.         One. low-pressure Safety Injection pump is operable. on each bus.
: d.       One high-pressure Safety Injection pump is operable on.each bus.
: e.         Both shutdown heat* exchangers and both component cooling heat exchanger~_    are operable.
f.* Piping and           valve~ shall be operable to provide two flow paths from the SIRW tank to the primary cooling system.
: g.         All valves,. pip&#xb5;ig _and interlocks associated with the-above components and required to function during accident conditions are operable.
: h.         The Low-Pressure Safety Injection Plow* Control Valve CV-3006 shall
                                        .be opened and disabled (by isolating the air supply) to prevent spurioua closure.         *
                                                                                '                                       .
: i.         The Safety Injection bottle motor~operated              isolation valves shall be opened with the electric power supply to the valve motor disconnected.
: j.         The Safety Injection miniflow valves CV-3027 and 3056 shall be opened with HS-3027 and 3056 positions to maintain them open.
                                    -*           For<-+h~ 1-~~0l;r'I d V\ a.8- t'.!4d~ g,1 b JIr>'IO\ a&#xa2;T".a-i "'S""~T-... b.vJ 3~ f
                                    *1GJfo.1* S'a<f?"T'1 T...,j,;-r;-~ \&deg;'""'):::. 1-1?.2.l'i ,.s- l--"'i'.S"''..:.""d -ro h~
3-29 .                   Amendment No. 7i, 101_                       ,
                                    .                                     .                           February 10, 1987                     . _ :
          .:h ~ * {J . * *
* a... b ~ ~ C...:...V, ~-n. ;rl~ D ~eoT..J11 %~ o-., e 't}'-'e l l."o -t-ke~v1v~/lkt7 o1 <f"tJJJ pow-lA, p>--1hYlt:t.114 ~oc\o.:...,j s-11..?}'.                  b                      ~-      ; -                    -
TSP1285-03S4;..NL04
                                                  - * -1J
                                                                      .          ~
                                                          ~t!..eed ;J..o~opp,,.,..,....
                                                                                              &deg;' C/Y\ ~~
1 ~l\ """'/ b vT/l'\OT}}

Revision as of 19:45, 21 October 2019

Proposed Tech Specs Reducing Min Allowable Boron Concentration in Safety Injection Tank T-82A During Period 900516-0930
ML18054B553
Person / Time
Site: Palisades Entergy icon.png
Issue date: 04/11/1990
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18054B552 List:
References
NUDOCS 9004200740
Download: ML18054B553 (7)


Text

SIT FILL AND DRAIN I SAMPL*E LINEUP SIRWT

  • -0"1Nl 00 -*-~
uo

-1:1!.

llJ .

l>O T-82 T-82 00

~8

._~SAMPLE SINK 0-0 gg

-08~

zru~

CUI

~ ~* *(JI-**;-

  • /

I I

I CV-3069

/ i

--.:___J a

~:_:/

OTHER 2 SIT

....

F&D I PCV VALVES PC~......i-------------- -itb. . -Vl *.........._-r-PC~--------------1---Vl~ll-.I OIAROINO PUMPS

...,

ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES April 11, 1990 2 Pages OC0390-0005-NL02

~ TABLE 4.2.1 M~um Frequencies for Sampling FSAR Section Test Frequency Reference

1. Reacior Coolant Gross Activity Deter- 3 Times/7 days with* a None Samples mination maximum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> be-tween samples (T avg greater than 500°F).

Gross Gamma by Fission Continuous when T avg is None Product Monitor greater thant 500°F(l).

Isotopic analysis 1/14 days during power None for dose equivalent operation I~l31 concentration i

  • Radio chemical for 1/6 months (2) None E determination Isotopic analysis a) Once/4 hours, whenever for iodine, including dose equivalent I-131 I-131, 133, 135 exceeds 1.0 µCI/gram, and b) One sample between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> follow-ing a thermal power change exceeding 15%

of rated thermal power within a one hour period.

Chemistry (Cl and 02) 3 times/7 days with a maximum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> between samples (T avg greater than 210°F).

Chemistry (Fl) Once/30 days and follow-ing modifications or repair to the primary coolant system involving welding.

2. Reactor Coolant Boron Concentration Twice/Week None Boron
3. SIRW Tank Water Boron Concentration Monthly None Sample
4. Concentrated Boron Concentration Monthly None Boric Acid Tanks
5. SI Tanks Boron Concentration Monthly 6.1.2
  • I
  • For T-82A, for the remainder of Cycle 8 but not after I September 30, 1990, following a PCS boron change greater I than 80 ppm below the equivalent hot full power value, I a sample will be taken within one hour. I 4-14 Amendment No. l~. 7<<, tti, OC0390-0005-NL02

3.3 EMERGENCY CORE COOLING SYSTEM Applicability Applies to the operating status of the emergency core cooling system.

Objective To assure operability of equipment required to remove decay heat from the core in either emergency or normal shutdown situations.

Specifications Safety Injection and Shutdown Cooling Systems 3.3.1 The reactor shall not be made critical, except for low-temperature physics tests, unless all of the following conditions are met:

a. The SIRW tank contains not less than 250,000 gallons of water with a boron concentration of at least 1720 ppm but not more than 2000 ppm at a temperature not less than 40°F.
b. All four Safety Injection tanks are operable and pressurized to at least 200 psig with a tank liquid level of at least 186 inches (55.5%) and a maximum level of 198 inches (59%) with a boron *.

concentration of at least 1720 ppm but not more than 2000 ppm. I

c. One low-pressure Safety Injection pump is operable on each bus.
d. One high-pressure Safety Injection pump is operable on each bus.
e. Both shutdown heat exchangers and both component cooling heat exchangers are operable.
f. Piping and valves shall be operable to provide two flow paths from the SIRW tank to the primary cooling system.
g. All valves, piping and interlocks associated with the above components and required to function during accident conditions are operable.
h. The Low-Pressure Safety Injection Flow Control Valve CV-3006 shall be opened and disabled (by isolating the air supply) to prevent spurious closure.
i. The Safety Injection bottle motor-operated isolation valves shall be opened with the electric power supply to the valve motor disconnected.
j. The Safety Injection miniflow valves CV-3027 and 3056 shall be opened with HS-3027 and 3056 positions to maintain them open.
  • For the remainder of Cycle 8, but not after September 30, 1990, Safety I Injection Tank T-82A is required to have a boron concentration greater than I or equal to the equivalent hot full power primary coolant system boron I concentration, but not to exceed 2000 ppm. I 3-29 Amendment No. 7<<, t~t.

OC0390-0005-NL02

ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 MARKED UP TECHNICAL SPECIFICATION PAGES April 11, 1990 2 Pages OC0390-0005-NL02

'

.'

TABLE 4.2.1 Minimum Frequencies for. Sampling Tests.' .:.;*1

. '.';

.r""-* .,, <~*~

FSAR ,

Section -- :: $

Test* Frequency *Reference l* Reactor Coolant Gross Activity Deter- 3 Times/7 days with a None Samples*

  • mination maximum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> be-tween samples (T avg greater than 500°F).

Gross Gamma. by Fission . Continuous when T'avg is None .:

Product Monitor greater thant 500°F(l).

Isotopic analysis 1/14 days during power None for dose equivalent operation*

. I-131 concentration Radio chemical for 1/6 months (2) - None E determination Isotopic analysis a) Once/4 hours, whenever for iodine, including dose equivalent I-131 I-131, 133, 135 exceeds 1.0 µCI/gram, and b) One sauiple between

.2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> follow-ing a thermal power.

change exceeding 15%

of rated thermal power within a one hour period.

Chemistry- (Cl and 02) 3 times/7 days with a maximum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> between samples (T avg greater than 210°F).

Chemistry (Fl) Once/30 days and follow-ing modifications or repair to the primary coolant system involving welding.

2. Reactor Coolant. Boron Concentration Twice/Week Norte Boron
3. SIRW Tank Water Boron Concentration Monthly None
  • sample
4. Concentrated** Boron Concentration Monthly None Boric Acid Tanks
6. 1. 2 ~ I
  • 5.
  • '. S SI Tanks e..pT~ b.J1.;J Boron* Concentration

.30/ /q?D,1 JJc: .t/ow1rio Monthly For--T-~,:J.A 1 .p.c:n -li.t.. ~e,,,;;~4e~~/~ ~,,, bvT~~-r 4j'r~

.t!t- pr1"'11'1t:v1'1 c.oo/C;rl/..S:~sT~

. I j

Po1WJ c/JPn')c..e_ ~C)..12t>J41 c/h~4~f Pf'  :;i q Sa-n/71~ U/ll/. -

1. ---1---:* I * - ul . _..,,A )op)- Amendment No. Z0. 11** 11.

p{!_ ./ O/~ e.VI TF-1 'l'1 ..,.,~ * ' March 25, 1988 TSP0987-0155-NL04

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-~

. .J "****

J * ~-

3.3 EMERGENCY CORE COOLING SYSTEM

~: . '.: .

. _ Applicability ,

  • .~--**
    • -

. Applies, co. the operacing status of the emergency core cool*ing system.

~--N Objective To ci.ssu*ra* operability of equipment required: to* remove decay heat from

  • the core in either emergency or normal shutdown s~tuations.

Specifications*

Safety Injection and Shutdown Cooling System&

3. 3. l The reactor shall not be made cr.1tical ~ except for low-temperature physics tests, unless all of the* following conditions are.met:
a. The SIRW tank contains not less than* 250,000 gallons of water with a boron concentration of at least 1720 ppm but not more than 2000 ppm. at a temperature not less than_ 40°r. .
b. All four Safety Injection tanks are operable and pressuriZed to~at
  • least 200 psig wit~ a tank liquid level of at least 186 inches .-;:

(55.5%) and a maximum. level of 198 inches (59%) with a boron _*

concentration of at least 1720 ppm but not more than 2000 ppm *.f * .j

c. One. low-pressure Safety Injection pump is operable. on each bus.
d. One high-pressure Safety Injection pump is operable on.each bus.
e. Both shutdown heat* exchangers and both component cooling heat exchanger~_ are operable.

f.* Piping and valve~ shall be operable to provide two flow paths from the SIRW tank to the primary cooling system.

g. All valves,. pipµig _and interlocks associated with the-above components and required to function during accident conditions are operable.
h. The Low-Pressure Safety Injection Plow* Control Valve CV-3006 shall

.be opened and disabled (by isolating the air supply) to prevent spurioua closure. *

' .

i. The Safety Injection bottle motor~operated isolation valves shall be opened with the electric power supply to the valve motor disconnected.
j. The Safety Injection miniflow valves CV-3027 and 3056 shall be opened with HS-3027 and 3056 positions to maintain them open.

-* For<-+h~ 1-~~0l;r'I d V\ a.8- t'.!4d~ g,1 b JIr>'IO\ a¢T".a-i "'S""~T-... b.vJ 3~ f

  • 1GJfo.1* S'a<f?"T'1 T...,j,;-r;-~ \°'""'):::. 1-1?.2.l'i ,.s- l--"'i'.S"..:.""d -ro h~

3-29 . Amendment No. 7i, 101_ ,

. . February 10, 1987 . _ :

.:h ~ * {J . * *

  • a... b ~ ~ C...:...V, ~-n. ;rl~ D ~eoT..J11 %~ o-., e 't}'-'e l l."o -t-ke~v1v~/lkt7 o1 <f"tJJJ pow-lA, p>--1hYlt:t.114 ~oc\o.:...,j s-11..?}'. b ~-  ; - -

TSP1285-03S4;..NL04

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~t!..eed ;J..o~opp,,.,..,....

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