ML19317H248: Difference between revisions
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{{#Wiki_filter:}} | {{#Wiki_filter:- . . - - - - | ||
_ | |||
, , , | |||
, | |||
.- 43 ,' | |||
' | |||
. | |||
800505093 9 (I) The engineered safety features valves associated with each of the above systems shall be operable or locked in the ES position. | |||
. | |||
3.3.2 In addition to 3.3.1 above, the following ECCS equipment shall be operable when the reactor coolant system is above 350F and irradi-ated fuel is in the core: | |||
_ | |||
(A) Two out of three high pressure injection (makeup) pumps shall be maintained operable, pcwcred from independent essential busses, to provide redundant and independent flow paths . | |||
(B) Engineered safety features valves associated with 3.3.2.a above shall be operable or locked in the ES position. | |||
3.3.3 In addition to 3.3.1 and 3.3.2 above, the following ECCS equipment shall be operabic when the reactor coolant system is above 800 psig: | |||
(A) The two core flooding tanks shall each contain an indicated minimum of 13 + 0.4 feet (1040 + 30 ft 3) of borated water at 600 3 25 psig.~ ~ | |||
(B) Core flooding tank boron concentration shall not be less than 2270 ppm boron. | |||
(C) The cicetrically operated discharge valves from the core flood tanks shall be open and breakers locked open and tagged. | |||
. | |||
(D) One of the two pressure instrument channels and one of the two icyc1 ins trument channels per core flood tank shall be operable. | |||
3.3.4 The reactor shall not be made critical unless the following equipment in addition to 3.3.1, 3.3. 2, and 3. 3. 3 ' above is operable. | |||
(A) Two reactor building spray pumps and their associated spray no::1c headers and four reactor building emergency' cooling fans and associated cooling units. . | |||
I (B) The sodium hydroxide tank shall contain an indicated 31 ft. | |||
of 20 wtt solution sodium hydroxide (20,500 lb.). | |||
. | |||
- | |||
~(C)1 ,A11 manual valves in the main discharge lines of the sodium thiosulfate and sodium hydroxide tanks shall be locked open. | |||
(0) Engineered safety feature valves and interlocks associated with 3.3.1, 3;3.2, and 3.3.3 shall be operable or locked in the ES position. | |||
3.3.5 Maintenance-shall be allowed during power operation on any component (s) in the high pressure injection, low pressure injection, service water, reactor building spray and reactor building cooling 37 Amendment No.''_ | |||
_ - - . ..-- _. -. _. . . _ . . | |||
. y. . | |||
, , . - . | |||
* | |||
- | |||
fp 41 e* | |||
. , . . | |||
'''. < | |||
'' | |||
Table h.1-1"(cont'd)' * | |||
, | |||
Channel De'scription - . Check. . Test ~ Calibrate Remarks | |||
' | |||
f37. " Boric?A cid Addition'Ta'k n > | |||
.4 | |||
: a. " Level Channel' :- NA NA R. | |||
::. , | |||
'b. ' Temperature Channel. -M NA LR . | |||
: 38. ' (DELETED) | |||
.. | |||
l- | |||
-39. Sodium Rydroxide Tank NA NA R l '; . ' Level Indicator | |||
' | |||
10. | |||
4 Incore Neutron, Detectors M(1) 'NA 'NA (1) Check Functionin6 a .hl. Erergency Plant Radiation Y' -Instruments- M(1) NA R (1) ' Battery Check | |||
: 42. ~ Deleted' h3. -Strong Motion Acceleographs Q(1) NA. Q (1) Battery Check hh. ESAS Manual. Trip Functions | |||
: a. Switches.&~ Logic NA R NA | |||
: b. Logic NA M NA h5 tReactor Manual Trip LNA P NA h6. Reactor Building Sump Level .NA NA R | |||
-Note: S .Each Shift .T/W'- Twice per Week R - Each Refueling Period | |||
.[ | |||
D - Daily. B/M - Every 2 Months NA - Not Applicable W - Weekly Q - Quarterly | |||
. | |||
M - Monthly- P - Prior to Each Startup if | |||
~ | |||
Not Done Previous Week | |||
,w n, . < | |||
- . | |||
..- | |||
, | |||
a . | |||
. . .,,.a. .. . , . , _ -, Tr.ble 4.1 * | |||
. | |||
_ | |||
MinaMUM SAMPLING.AND ANALYSIS FREQUENCY | |||
. .s | |||
' _! t em - , --) . Test' Frecuency | |||
: 1. Reactor Coolant a. Gamma Isotopic' Analysis a. | |||
Samples Bi-weekly (7) | |||
, b. ' Gross Activity-Deternination b. 3 times / week ar.- | |||
- | |||
at least every third oay(1),o',,- | |||
: c. ' Gross Radioiodine Determination c. Weekly (3)(6)(7) | |||
: d. Dissolved Cases d. Week l y ' ( 7 )(11) l> | |||
: e. Chemistry (C1, F, and 02 ) c. | |||
3 times / week (5) f. | |||
Boron Concentration f. 3 times / week | |||
* | |||
: g. Radiochemical Analysis for g. Monthly (7) | |||
~f Determination' (2)(4) | |||
: 2. Dorated hater Storage Tank Water Boron Concentration Weekly and af t er Sampic each makeup I | |||
, | |||
~3. Cope flooding Tank Sample Boron Concentration Monthly and after cach nakeup 4 -Spent Fuct Pool Water Sample Boron Concentration Monthly and after ~ , | |||
each makeup-(9', | |||
: 5. ~ Secondary Coolant a. | |||
Sampies. . Gross Radioiodine' Concentration a. Weekly (5)(7)(10) | |||
: b. Isotopic Radioiodine b. Monthly (7)(10' ~ | |||
Concentration (4) | |||
'6. Sodium Ilydroxide Sodium Ilydroxide Concentration Quarterly and Tank Samp~ie ' | |||
after each makeus | |||
- | |||
No t e s': ' | |||
,. . | |||
. | |||
! | |||
! | |||
-(1) | |||
_ of; the -total radioactivity of the primary coolant. A gross radioactivit in units of uCi/gm. The total primary coolant activity shall be the sum of the degassed beta-gamma act ivity and the' total 'of 'all. identified gaseous activities 15 minutes | |||
. | |||
- | |||
af ter the primary system is ' sampled. | |||
, | |||
concentration execeds -10'. .of the limitWhenever the gross radioactivity | |||
~ | |||
' | |||
specified in the Specification 3.1.4.1- or increases .hv IO. LCi/g . from the previous nr. asured level, the fregttency of _ sa.r.plini; and analy ir.g -sh.1-1 he increased ,to a minimum of-once/ day until .a steady activity ' level as established. | |||
- | |||
, ,; | |||
- ' 74 - | |||
, | |||
Amendment No. 12 | |||
, | |||
4 | |||
,b s | |||
. | |||
Nsb;Rv.195 v.s. NUCLEAn REGULATORY COMMISSICN QQCKET NUMEE R (2 des ' * * . | |||
}/ 9Jef $~ 3d | |||
''''"""''" - | |||
.' NRC DISTR'IBUTION ron PA / 50 DOCKET MATERIAL | |||
"*** DAVI5 FROMARKANSAS POWER & LIGHT C0 cars CP oCCUMENT TO: | |||
f LITTLE ROCK, ARKANSAS 7/5/77 | |||
* J.D. PHILLIPS cATE RECE!VED | |||
! 7/5/77 j %EnER ONOTORIZIO PRCP lNPUT PCRM NUMBER OF COPIES RECEIVED l RIGIN AL MNCLASSIPIE D | |||
; QESCRIPTION ENCLOSURE | |||
; ,7 ..,.,_ .: | |||
' | |||
- '"~ - % | |||
} | |||
' | |||
f Amdt, to OL/changg' to tech specs... | |||
concerns the deletion of Sodium Thiosulphate e | |||
;/ 'romtheReactor(uildingSpraySystem...... | |||
, , | |||
. | |||
! | |||
. | |||
?.h (1-P ) (3-P) ./ . | |||
/-'T~M.T | |||
_.?ff. | |||
. i.1.w W .' N .,Tv d-N.V vn | |||
. . . . . . _ , . I PLANT NAME: Arkansas Unit No.1 RJL 7/12/77 cappy FOR ACTION /INFORMATION ENVIPENMENTAL I ASSIGNED ADe _ _ s l' ASSIGNED AD: V. MOORE (LTR) t/f nRANcM cu7pp, D au p ,3, ( g) BRANCH CHIEF: | |||
IM PROJECT MANAGER: $nMdO PROJECT MANAGER: | |||
~ | |||
VI LICENSING ASSISTANT: O [ -C ( .$. LICENSING ASSISTANT: | |||
, | |||
i B. HARLESS 1 INTERNAL DISTRIBUTION l/. een rT f E q SYS'TFMS SAFEIY PLANT SYSTEMS I SITE SAFEIY & | |||
f/ Nur pnR . HEINEMAN TEDESCO ENVIRON ANALYSIS 767 a, y ( 2) SCHROEDER BENAROYA DENTON & MULLER | |||
/ n et n LATNAS CR17CMrTrfD | |||
' | |||
COSSICK & STAFF ENGINEERING IPPOLITO - | |||
A tiivattv7 KNTCMT F. ROSA ENVIRO TECH. | |||
3 I VTpc nOSNAK ERNST l j cur . V SIHWELL IOPERATING REACTORS BALLARD l Iunvn PAWLTcKI ' | |||
STELLO YOUNGBLOOD I /, ETcFNMTfT l ormrcT MANACrvrNT ' | |||
REACTOR SAFETV d SHAO _ __. _. _.. | |||
" ' ~ ^ ~ ~ | |||
* Ievnvuot? ROSS /] BAER I o. cotLINS NOVAK /l BUTLER GAMMILL (2) unUS'mN ROSZTOCZY / GRIMES vetT" CHECK SITE ANALYSIS urtreveq l VOLLER eT AT&T I l BUNCH ISALTZv_AN I l / J. COLLINS IRL~' BERG I l KREGER l _ .. | |||
,. EXTERN AL DISTRIBUTION CONTROL NUMBE R i A1?ca V,su tilo,Ile MKK l l | |||
/I TIC | |||
' ' | |||
#M NSIC l l ~ | |||
INAT LAB i l h).2 iREG IV (J. HANCHETT)i I / | |||
i/ | |||
r ,16 CYS ACRS SENT CATEGORY , , | |||
4 i , | |||
I | |||
= | |||
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. . . . . . . . . . . . . . . . | |||
. ~ | |||
f}} |
Revision as of 06:39, 14 December 2019
ML19317H248 | |
Person / Time | |
---|---|
Site: | Arkansas Nuclear |
Issue date: | 07/05/1977 |
From: | ARKANSAS POWER & LIGHT CO. |
To: | |
Shared Package | |
ML19317H247 | List: |
References | |
NUDOCS 8005050435 | |
Download: ML19317H248 (4) | |
Text
- . . - - - -
_
, , ,
,
.- 43 ,'
'
.
800505093 9 (I) The engineered safety features valves associated with each of the above systems shall be operable or locked in the ES position.
.
3.3.2 In addition to 3.3.1 above, the following ECCS equipment shall be operable when the reactor coolant system is above 350F and irradi-ated fuel is in the core:
_
(A) Two out of three high pressure injection (makeup) pumps shall be maintained operable, pcwcred from independent essential busses, to provide redundant and independent flow paths .
(B) Engineered safety features valves associated with 3.3.2.a above shall be operable or locked in the ES position.
3.3.3 In addition to 3.3.1 and 3.3.2 above, the following ECCS equipment shall be operabic when the reactor coolant system is above 800 psig:
(A) The two core flooding tanks shall each contain an indicated minimum of 13 + 0.4 feet (1040 + 30 ft 3) of borated water at 600 3 25 psig.~ ~
(B) Core flooding tank boron concentration shall not be less than 2270 ppm boron.
(C) The cicetrically operated discharge valves from the core flood tanks shall be open and breakers locked open and tagged.
.
(D) One of the two pressure instrument channels and one of the two icyc1 ins trument channels per core flood tank shall be operable.
3.3.4 The reactor shall not be made critical unless the following equipment in addition to 3.3.1, 3.3. 2, and 3. 3. 3 ' above is operable.
(A) Two reactor building spray pumps and their associated spray no::1c headers and four reactor building emergency' cooling fans and associated cooling units. .
I (B) The sodium hydroxide tank shall contain an indicated 31 ft.
of 20 wtt solution sodium hydroxide (20,500 lb.).
.
-
~(C)1 ,A11 manual valves in the main discharge lines of the sodium thiosulfate and sodium hydroxide tanks shall be locked open.
(0) Engineered safety feature valves and interlocks associated with 3.3.1, 3;3.2, and 3.3.3 shall be operable or locked in the ES position.
3.3.5 Maintenance-shall be allowed during power operation on any component (s) in the high pressure injection, low pressure injection, service water, reactor building spray and reactor building cooling 37 Amendment No._
_ - - . ..-- _. -. _. . . _ . .
. y. .
, , . - .
-
fp 41 e*
. , . .
. <
Table h.1-1"(cont'd)' *
,
Channel De'scription - . Check. . Test ~ Calibrate Remarks
'
f37. " Boric?A cid Addition'Ta'k n >
.4
- a. " Level Channel' :- NA NA R.
- . ,
'b. ' Temperature Channel. -M NA LR .
- 38. ' (DELETED)
..
l-
-39. Sodium Rydroxide Tank NA NA R l '; . ' Level Indicator
'
10.
4 Incore Neutron, Detectors M(1) 'NA 'NA (1) Check Functionin6 a .hl. Erergency Plant Radiation Y' -Instruments- M(1) NA R (1) ' Battery Check
- 42. ~ Deleted' h3. -Strong Motion Acceleographs Q(1) NA. Q (1) Battery Check hh. ESAS Manual. Trip Functions
- a. Switches.&~ Logic NA R NA
- b. Logic NA M NA h5 tReactor Manual Trip LNA P NA h6. Reactor Building Sump Level .NA NA R
-Note: S .Each Shift .T/W'- Twice per Week R - Each Refueling Period
.[
D - Daily. B/M - Every 2 Months NA - Not Applicable W - Weekly Q - Quarterly
.
M - Monthly- P - Prior to Each Startup if
~
Not Done Previous Week
,w n, . <
- .
..-
,
a .
. . .,,.a. .. . , . , _ -, Tr.ble 4.1 *
.
_
MinaMUM SAMPLING.AND ANALYSIS FREQUENCY
. .s
' _! t em - , --) . Test' Frecuency
- 1. Reactor Coolant a. Gamma Isotopic' Analysis a.
Samples Bi-weekly (7)
, b. ' Gross Activity-Deternination b. 3 times / week ar.-
-
at least every third oay(1),o',,-
- c. ' Gross Radioiodine Determination c. Weekly (3)(6)(7)
- d. Dissolved Cases d. Week l y ' ( 7 )(11) l>
- e. Chemistry (C1, F, and 02 ) c.
3 times / week (5) f.
Boron Concentration f. 3 times / week
- g. Radiochemical Analysis for g. Monthly (7)
~f Determination' (2)(4)
- 2. Dorated hater Storage Tank Water Boron Concentration Weekly and af t er Sampic each makeup I
,
~3. Cope flooding Tank Sample Boron Concentration Monthly and after cach nakeup 4 -Spent Fuct Pool Water Sample Boron Concentration Monthly and after ~ ,
each makeup-(9',
- 5. ~ Secondary Coolant a.
Sampies. . Gross Radioiodine' Concentration a. Weekly (5)(7)(10)
- b. Isotopic Radioiodine b. Monthly (7)(10' ~
Concentration (4)
'6. Sodium Ilydroxide Sodium Ilydroxide Concentration Quarterly and Tank Samp~ie '
after each makeus
-
No t e s': '
,. .
.
!
!
-(1)
_ of; the -total radioactivity of the primary coolant. A gross radioactivit in units of uCi/gm. The total primary coolant activity shall be the sum of the degassed beta-gamma act ivity and the' total 'of 'all. identified gaseous activities 15 minutes
.
-
af ter the primary system is ' sampled.
,
concentration execeds -10'. .of the limitWhenever the gross radioactivity
~
'
specified in the Specification 3.1.4.1- or increases .hv IO. LCi/g . from the previous nr. asured level, the fregttency of _ sa.r.plini; and analy ir.g -sh.1-1 he increased ,to a minimum of-once/ day until .a steady activity ' level as established.
-
, ,;
- ' 74 -
,
Amendment No. 12
,
4
,b s
.
Nsb;Rv.195 v.s. NUCLEAn REGULATORY COMMISSICN QQCKET NUMEE R (2 des ' * * .
}/ 9Jef $~ 3d
''"""" -
.' NRC DISTR'IBUTION ron PA / 50 DOCKET MATERIAL
"*** DAVI5 FROMARKANSAS POWER & LIGHT C0 cars CP oCCUMENT TO:
f LITTLE ROCK, ARKANSAS 7/5/77
- J.D. PHILLIPS cATE RECE!VED
! 7/5/77 j %EnER ONOTORIZIO PRCP lNPUT PCRM NUMBER OF COPIES RECEIVED l RIGIN AL MNCLASSIPIE D
- QESCRIPTION ENCLOSURE
- ,7 ..,.,_ .
'
- '"~ - %
}
'
f Amdt, to OL/changg' to tech specs...
concerns the deletion of Sodium Thiosulphate e
- / 'romtheReactor(uildingSpraySystem......
, ,
.
!
.
?.h (1-P ) (3-P) ./ .
/-'T~M.T
_.?ff.
. i.1.w W .' N .,Tv d-N.V vn
. . . . . . _ , . I PLANT NAME: Arkansas Unit No.1 RJL 7/12/77 cappy FOR ACTION /INFORMATION ENVIPENMENTAL I ASSIGNED ADe _ _ s l' ASSIGNED AD: V. MOORE (LTR) t/f nRANcM cu7pp, D au p ,3, ( g) BRANCH CHIEF:
IM PROJECT MANAGER: $nMdO PROJECT MANAGER:
~
VI LICENSING ASSISTANT: O [ -C ( .$. LICENSING ASSISTANT:
,
i B. HARLESS 1 INTERNAL DISTRIBUTION l/. een rT f E q SYS'TFMS SAFEIY PLANT SYSTEMS I SITE SAFEIY &
f/ Nur pnR . HEINEMAN TEDESCO ENVIRON ANALYSIS 767 a, y ( 2) SCHROEDER BENAROYA DENTON & MULLER
/ n et n LATNAS CR17CMrTrfD
'
COSSICK & STAFF ENGINEERING IPPOLITO -
A tiivattv7 KNTCMT F. ROSA ENVIRO TECH.
3 I VTpc nOSNAK ERNST l j cur . V SIHWELL IOPERATING REACTORS BALLARD l Iunvn PAWLTcKI '
STELLO YOUNGBLOOD I /, ETcFNMTfT l ormrcT MANACrvrNT '
REACTOR SAFETV d SHAO _ __. _. _..
" ' ~ ^ ~ ~
- Ievnvuot? ROSS /] BAER I o. cotLINS NOVAK /l BUTLER GAMMILL (2) unUS'mN ROSZTOCZY / GRIMES vetT" CHECK SITE ANALYSIS urtreveq l VOLLER eT AT&T I l BUNCH ISALTZv_AN I l / J. COLLINS IRL~' BERG I l KREGER l _ ..
,. EXTERN AL DISTRIBUTION CONTROL NUMBE R i A1?ca V,su tilo,Ile MKK l l
/I TIC
' '
- M NSIC l l ~
INAT LAB i l h).2 iREG IV (J. HANCHETT)i I /
i/
r ,16 CYS ACRS SENT CATEGORY , ,
4 i ,
I
=
~
I[
. . . . . . . . . . . . . . . .
. ~
f