Similar Documents at Fermi |
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20212H2861999-09-24024 September 1999 Proposed Tech Specs 3/4.6.1.8,allowing Continued Operation Until Next Plant Shutdown at Which Time Valve T4803F601 Will Be Repaired ML20212H4351999-09-24024 September 1999 Proposed Tech Specs Re Util Request for Enforcement Discretion with Respect to TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys ML20211Q1841999-09-10010 September 1999 Proposed Tech Specs Revising SRs & Bases for Div I Battery Sys to Agree with Design of New Battery Replacement ML20211Q7351999-09-0303 September 1999 Proposed Its,Rev 15 ML20211G0921999-08-25025 August 1999 Rev 14 Proposed ITS Pages,Providing Update for Remaining Open Issues Associated with NRC Review of ITS Submittal ML20211B9991999-08-0606 August 1999 Proposed Its,Rev 13 ML20210N0231999-08-0404 August 1999 Rev 12 to 980403 ITS Submittal,Providing Update to Submittal for ITS Sction 3.3,including Changes Associated with NRC Review of Rev 6 to ITS Submittal ML20210J1641999-07-30030 July 1999 Draft Proposed Tech Spec Pages Re Amend to License NPF-43 to Include Provisions for Enabling Oscillation Power Range Monitor (OPRM) Upscale Function in Average Power Range Monitor (APRM) ML20216D6091999-07-26026 July 1999 Rev 11 to ITS Submittal,Dtd 980403,providing Update to ITS Sections 3.5,3.6 & 3.8 ML20209H0331999-07-13013 July 1999 Rev 10 to ITS Submittal,Dtd 980403,providing Update to ITS Submittal for ITS Section 3.4,RCS ML20209D4001999-07-0707 July 1999 Rev 9 to Fermi 2 ITS Submittal Dtd 980403,providing Update for Sections 3.0,4.0 & 5.0 ML20196K1681999-07-0101 July 1999 Rev 8 to ITS Submittal Dtd 980403,providing Update to ITS Submittal for ITS Section 3.7 ML20196F4681999-06-24024 June 1999 Rev 7 to ITS Submittal of 980403 to Provide Remaining Responses to NRC RAIs Re ITS Sections 3.5 & 3.8 ML20212H5041999-06-0202 June 1999 Proposed Tech Specs Pages to Rev 6 of Fermi Unit 2 ITS ML20206M1121999-05-0707 May 1999 Proposed Tech Specs Section 3.6,converting to ITS ML20206H5521999-04-30030 April 1999 Proposed Rev 5 to Improved TS Pages ML20205T5361999-04-20020 April 1999 Marked-up & Typed Up Revised TS Pages Eliminating TS SR for Nitrogen Cover Gas on Nearly Empty Primary Sodium Storage Tanks in Sodium Bldg Complex ML20196K6621999-04-0202 April 1999 Proposed Tech Specs Re Rev 4 to Fermi 2 ITS Submittal ML20205A3201999-03-23023 March 1999 Proposed Tech Specs SR 4.4.1.1.1,requiring Each Recirculation Pump Discharge Valve Be Demonstrated Operable at Least Every 18 Months & Deleting Footnote That Applies to TS 4.4.1.1.1 & Stating *Not Used ML20202D9551999-01-26026 January 1999 Rev 2 to Fermi 2 Its,Incorporating Operating License Amends 119,122,128 & 129,issued Since Initial ITS Submittal Was Finalized ML20155A7111998-10-22022 October 1998 Proposed Replacement TS Sections F.1.a & F.2.b Pages, Utilizing Terminology of TEDE Instead of Whole Body & Organ Dose ML20154E5621998-09-28028 September 1998 Revised Proposed Tech Specs Pages Re 980403 Application for Amend to License NPF-43 for Conversion of TS to Improved Standard TS ML20237E8981998-08-26026 August 1998 Proposed Tech Specs Implementing Provisions of 1996 Decommissioning Rule,Including Requirements for Control of Effluents,Dose Limits,& Annual Reporting of 10CFR50.36a ML20236W4701998-07-31031 July 1998 Proposed Tech Specs 3.5.1 & 3.5.2 Re Footnote for Limiting Condition for Operation ML20236U4601998-07-23023 July 1998 Proposed Tech Specs Revising Table 4.0.2-1 to Include Two Functional Units for TS 4.3.1.3 (RPS Response Time Testing) & Allowing one-time Extension of Respective Surveillance Intervals ML20236U0421998-07-16016 July 1998 TS Insert Page & Associated Index Page Reflecting Withdrawal of Request for Extension of Surveillance Interval for TS 4.0.5,as Contained in Enclosure 20 of & Administrative Change ML20236F0671998-06-26026 June 1998 Proposed Tech Specs Allowing one-time Extension of Surveillance Intervals to Delay Shutdown for Upcoming Sixth Refueling Outage (RFO6) Until 980904 ML20248L8021998-06-0505 June 1998 Proposed Tech Specs Section 2.1.2,re Thermal Pressure,High Pressure & High Flow ML20248E4151998-05-28028 May 1998 Proposed Tech Specs Page 3/4 5-1,revised to Include Remaining Proposed Changes W/Applicability Restored to Reflect Original Notation Re Realignment of LPCI Sys ML20247Q1191998-05-20020 May 1998 Proposed Tech Specs Pages Revising TS 3.1.3.1,Action D to Apply to Valves Inoperable for Any Reason & Increase Time Allowed for Restoring SDV Vent or Drain Line W/One Valve Inoperable from Current 24 Hours to 7 Days ML20247A7401998-04-27027 April 1998 Proposed Tech Specs Pages,Adding Configuration Risk Mgt Program to TS Section 6.8.5 ML20216F6971998-04-0909 April 1998 Proposed Tech Specs,Withdrawing Previously Submitted Response Time Testing Requirement Clarification Re Neutron Monitoring Sys ML20216J7581998-04-0909 April 1998 Proposed Tech Specs 3.3.7.5,3.7.1.2 & 3.8.1.1 Re Alignment of Shutdown Action Statements for Primary Containment Oxygen Monitoring Instrumentation ML20216B3311998-04-0303 April 1998 Proposed Tech Specs,Extending EDG Allowed Times at Plant ML20217P0631998-04-0202 April 1998 Proposed Tech Specs Re Mod of Drywell Oxygen Monitoring Instrumentation Action Requirements to Be Consistent W/Those Contained in NUREG-1433 Rev 1, Std Tech Specs GE Plants BWR/4 ML20217P5691998-04-0202 April 1998 Proposed Tech Specs Changing Requirements Associated W/ Containment Oxygen & Hydrogen Monitors ML20217J5441998-03-27027 March 1998 Proposed Tech Specs Eliminating Incorrect Descriptive Info Re Water Inventory in CST Reserved for Hpci/Rcic & Raising CST Min Water Level for Core Spray ML20217J5841998-03-27027 March 1998 Proposed Tech Specs Revising Footnote Specifying Conditions Where Isolation Valves Associated W/Lpci Sys Operation Are Repositioned ML20199H9371998-01-28028 January 1998 Proposed Tech Specs Re thermal-hydraulic Stability,Idle Recirculation Loop Startup & Post Accident Monitoring ML20199H2611998-01-28028 January 1998 Proposed Tech Specs Re Access Control to Provide Flexibility While Maintaining Similar Control Over Access ML20199H2561998-01-28028 January 1998 Proposed Tech Specs,Modifying Sections F & I of Plant TS to Include Requirements for Control of Effluents,Dose Limits & Annual Requirements Per 10CFR50.36a ML20199H2501998-01-28028 January 1998 Proposed Tech Specs 4.4.3.2.2.a,changing Surveillance Interval in TS 4.4.3.2.2.a by Extending It from Current 18 Month Testing Interval to 24 Month Testing Interval to Be Consistent W/Asme Code Requirements ML20199H2411998-01-28028 January 1998 Proposed Tech Specs,Revising Footnotes Specifying Conditions Under Which SRs Associated W/Ts 3/4.9.1, Reactor Mode Switch Can Be Performed ML20199H2141998-01-28028 January 1998 Proposed Tech Specs,Revising SRs for Div II Battery Sys to Agree W/Design of New Battery Replacement ML20199H2281998-01-28028 January 1998 Proposed Marked Up & Retyped TS of Sheet 2,Table 3.3.6-2, Deleting RCS Recirculation Flow Trip Functions ML20203F1941997-12-10010 December 1997 Proposed Tech Specs Revising TS to Be Consistent W/Planned Replacement of Current Power Range Monitoring Portion of Existing Nms ML20202A7961997-11-26026 November 1997 Proposed Tech Specs Reflecting Alternative Wording for Surveillance Which Address Only Clarification to Situational Testing Requirement NRC-97-0089, Proposed Tech Specs,Relocating Selected Requirements & Bases from TS to Ufsar.Rev of TS Index & List of Tables to Reflect Relocation Requested1997-09-29029 September 1997 Proposed Tech Specs,Relocating Selected Requirements & Bases from TS to Ufsar.Rev of TS Index & List of Tables to Reflect Relocation Requested ML20216F3581997-09-0505 September 1997 Proposed Tech Specs,Adding Special Test Exception to Allow Unit to Remain in Operational Condition 4 W/Reactor Coolant Temps Greater than 200 F,But Less than 212 F,When Performing Inservice Leak & Hydrostatic Testing ML20141B8881997-06-20020 June 1997 Proposed Tech Specs Re Relocation of Reactor Recirculation Sys MG Set Scoop Tube Stop Setting Surveillance 1999-09-03
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212H4351999-09-24024 September 1999 Proposed Tech Specs Re Util Request for Enforcement Discretion with Respect to TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys ML20212H2861999-09-24024 September 1999 Proposed Tech Specs 3/4.6.1.8,allowing Continued Operation Until Next Plant Shutdown at Which Time Valve T4803F601 Will Be Repaired ML20211Q1841999-09-10010 September 1999 Proposed Tech Specs Revising SRs & Bases for Div I Battery Sys to Agree with Design of New Battery Replacement ML20211Q7351999-09-0303 September 1999 Proposed Its,Rev 15 ML20211G0921999-08-25025 August 1999 Rev 14 Proposed ITS Pages,Providing Update for Remaining Open Issues Associated with NRC Review of ITS Submittal ML20211B9861999-08-13013 August 1999 Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval ML20211C2631999-08-13013 August 1999 Rev 2,change 0 to ISI-Nondestructive Exam (ISE-NDE) Program (Plan) for Fermi 2 Power Plant, for Second ten-year Interval ML20211B9991999-08-0606 August 1999 Proposed Its,Rev 13 ML20210N0231999-08-0404 August 1999 Rev 12 to 980403 ITS Submittal,Providing Update to Submittal for ITS Sction 3.3,including Changes Associated with NRC Review of Rev 6 to ITS Submittal ML20210J1641999-07-30030 July 1999 Draft Proposed Tech Spec Pages Re Amend to License NPF-43 to Include Provisions for Enabling Oscillation Power Range Monitor (OPRM) Upscale Function in Average Power Range Monitor (APRM) ML20216D6091999-07-26026 July 1999 Rev 11 to ITS Submittal,Dtd 980403,providing Update to ITS Sections 3.5,3.6 & 3.8 ML20209H0331999-07-13013 July 1999 Rev 10 to ITS Submittal,Dtd 980403,providing Update to ITS Submittal for ITS Section 3.4,RCS ML20209D4001999-07-0707 July 1999 Rev 9 to Fermi 2 ITS Submittal Dtd 980403,providing Update for Sections 3.0,4.0 & 5.0 ML20196K1681999-07-0101 July 1999 Rev 8 to ITS Submittal Dtd 980403,providing Update to ITS Submittal for ITS Section 3.7 ML20210A3031999-06-30030 June 1999 Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan ML20196F4681999-06-24024 June 1999 Rev 7 to ITS Submittal of 980403 to Provide Remaining Responses to NRC RAIs Re ITS Sections 3.5 & 3.8 ML20212H5041999-06-0202 June 1999 Proposed Tech Specs Pages to Rev 6 of Fermi Unit 2 ITS ML20206M1121999-05-0707 May 1999 Proposed Tech Specs Section 3.6,converting to ITS ML20206M8651999-05-0606 May 1999 Rev 30,Vol I to Technical Requirements Manual ML20206H5521999-04-30030 April 1999 Proposed Rev 5 to Improved TS Pages ML20205T5361999-04-20020 April 1999 Marked-up & Typed Up Revised TS Pages Eliminating TS SR for Nitrogen Cover Gas on Nearly Empty Primary Sodium Storage Tanks in Sodium Bldg Complex ML20196K6621999-04-0202 April 1999 Proposed Tech Specs Re Rev 4 to Fermi 2 ITS Submittal ML20205A3201999-03-23023 March 1999 Proposed Tech Specs SR 4.4.1.1.1,requiring Each Recirculation Pump Discharge Valve Be Demonstrated Operable at Least Every 18 Months & Deleting Footnote That Applies to TS 4.4.1.1.1 & Stating *Not Used ML20202D9551999-01-26026 January 1999 Rev 2 to Fermi 2 Its,Incorporating Operating License Amends 119,122,128 & 129,issued Since Initial ITS Submittal Was Finalized ML20198D1391998-12-14014 December 1998 Rev 28 to Vol 1 of Technical Requirements Manual ML20198B8121998-12-10010 December 1998 Rev 27 to Fermi 2 Technical Requirements Manual,Vol I ML20155A7111998-10-22022 October 1998 Proposed Replacement TS Sections F.1.a & F.2.b Pages, Utilizing Terminology of TEDE Instead of Whole Body & Organ Dose ML20154Q0771998-10-15015 October 1998 6 to Fermi 2, Technical Requirements Manual, Vol I ML20154M4611998-10-0909 October 1998 5 to Vol 1 of Fermi 2 Technical Requirements Manual ML20154H8931998-10-0808 October 1998 Rev 24 to Fermi 2 Technical Requirements Manual,Vol I ML20154E5621998-09-28028 September 1998 Revised Proposed Tech Specs Pages Re 980403 Application for Amend to License NPF-43 for Conversion of TS to Improved Standard TS ML20153F3931998-09-23023 September 1998 Rev 23 to Fermi 2 Technical Requirements Manual,Vol 1 ML20237E8981998-08-26026 August 1998 Proposed Tech Specs Implementing Provisions of 1996 Decommissioning Rule,Including Requirements for Control of Effluents,Dose Limits,& Annual Reporting of 10CFR50.36a ML20237D6311998-08-18018 August 1998 Rev 22 to Fermi 2 Technical Requirements Manual,Vol 1 ML20236W4701998-07-31031 July 1998 Proposed Tech Specs 3.5.1 & 3.5.2 Re Footnote for Limiting Condition for Operation ML20236U4601998-07-23023 July 1998 Proposed Tech Specs Revising Table 4.0.2-1 to Include Two Functional Units for TS 4.3.1.3 (RPS Response Time Testing) & Allowing one-time Extension of Respective Surveillance Intervals ML20236U0421998-07-16016 July 1998 TS Insert Page & Associated Index Page Reflecting Withdrawal of Request for Extension of Surveillance Interval for TS 4.0.5,as Contained in Enclosure 20 of & Administrative Change ML20236F0671998-06-26026 June 1998 Proposed Tech Specs Allowing one-time Extension of Surveillance Intervals to Delay Shutdown for Upcoming Sixth Refueling Outage (RFO6) Until 980904 ML20236P9241998-06-10010 June 1998 Rev 20 to Fermi 2 Technical Requirements Manual, Vol 1 ML20248L8021998-06-0505 June 1998 Proposed Tech Specs Section 2.1.2,re Thermal Pressure,High Pressure & High Flow ML20248H0901998-05-31031 May 1998 Vol 1,Rev 19 to Technical Requirements Manual for Fermi 2 ML20248E4151998-05-28028 May 1998 Proposed Tech Specs Page 3/4 5-1,revised to Include Remaining Proposed Changes W/Applicability Restored to Reflect Original Notation Re Realignment of LPCI Sys ML20247Q1191998-05-20020 May 1998 Proposed Tech Specs Pages Revising TS 3.1.3.1,Action D to Apply to Valves Inoperable for Any Reason & Increase Time Allowed for Restoring SDV Vent or Drain Line W/One Valve Inoperable from Current 24 Hours to 7 Days ML20247A7401998-04-27027 April 1998 Proposed Tech Specs Pages,Adding Configuration Risk Mgt Program to TS Section 6.8.5 ML20216F6971998-04-0909 April 1998 Proposed Tech Specs,Withdrawing Previously Submitted Response Time Testing Requirement Clarification Re Neutron Monitoring Sys ML20216J7581998-04-0909 April 1998 Proposed Tech Specs 3.3.7.5,3.7.1.2 & 3.8.1.1 Re Alignment of Shutdown Action Statements for Primary Containment Oxygen Monitoring Instrumentation ML20216B3311998-04-0303 April 1998 Proposed Tech Specs,Extending EDG Allowed Times at Plant ML20217P5691998-04-0202 April 1998 Proposed Tech Specs Changing Requirements Associated W/ Containment Oxygen & Hydrogen Monitors ML20217P0631998-04-0202 April 1998 Proposed Tech Specs Re Mod of Drywell Oxygen Monitoring Instrumentation Action Requirements to Be Consistent W/Those Contained in NUREG-1433 Rev 1, Std Tech Specs GE Plants BWR/4 ML20217J5841998-03-27027 March 1998 Proposed Tech Specs Revising Footnote Specifying Conditions Where Isolation Valves Associated W/Lpci Sys Operation Are Repositioned 1999-09-03
[Table view] |
Text
W WO g O OP w P P o n L f l i L LA o f t A AM f n t M MR s o d o e R RE -
n e i s E EH o s t t H HT i n a a p E T
- T s s o r i i U % % D p i i v r L 3 D 5 DE c v s f e t A 4 E 4 ET i i o d V T TA 5 d v e
+ A + AR 0 e ie % w h E R R 1 5l dl 5 o T L W W f
1c 5c "0 1 f A 6 o 6 o /s 2s
'1 / .
W 6 6 % 6 c 0 1 1 % )
O % %4 1l 9 1 W L
L 0
A 3 0 A
31 A
1 A
2 A
1l uA
/n 3
u 5
A 1
A 1
1 A
(
A <N> <N>5 N<R>_ N<TN>T <N <NiN w o
l f
e v
i R r R RE d .
S E EW 2 T W WO p N O OP w o2 I P P o o O .L f l l 3 .
P L LA o f T A AM f n nn E
S M
R MR RE s
n o d o oo e i ii E EH o s t t tt N H HT i n a a aa 2 O T
- T s s o r i l c I % % D p i i v ui T T 0 D 2 DE c v s f e cf A N 4 E 4 ET i i o d ri o 2 T I T TA s d v i c +
O + A + AR e % w ce r 6
- N E
M P
T W R
W R
f 0
1
\"
1 5
2 l o ep rS 3 U E f f o x s 1c 5 c 1 1 f R S 6 o 6 o p /s 2s / fh 3 T S P 6
6
%2
% 0 c 8 0l 1
/
'9 8
8 0
0 ot E N L I I
R 0
A 5 0 A
51 A
1 A
3 A
1l uA 5Hu 5 A
1 A
1 A
nw o
i _
B T N> <N>3 N<N>_ N<TN> <N <H5N i e A K -
tc 6 T C cn O
L na ud ,
o B f r -
W o D O ac O L c R F sa N a
'L N O n O h g
n O I di .
R w I T e O
T N
i H d t
o T A
L I
S O
id re an C - e U P vi x
S C R N st a
u ,
S I W in l e R C O i ,
F l O E D na n
a c i n T n I i R .
T U i om o s N E M H t e r p S l O l M s E S cb t U R l M l U hs T n u O u u L ga S H ut e ' - T f E f O ip Y C f s R N I G V Hy S T u i O x N t N t B I km s T
I e
v d e ev l u O o M n e
v A o R n e
v E
G ep l T N
e vr S W c on .
N i e sieF ie ie R vi A io l o .
O tl atl E r tl E r tl A er L tt E bi M eaa iaan G oeaa T oe aa H LT O eaa D t .
l rc Brco N tl rc A tl rc C O l rr O dc N K aes O C cpn esr A caes I wpnt R ecpn D ec ca es S pn I rm ea C aea cpp M on ru I O sow pno oowu t sow E t s ow D t r R som R f T L C B UID l noe E epno M ep no ac O pno O M FIDN C DUID R DU ID M WS T UIC T R s N M R E A C C Pi U D U R A A F O R
. ..RP abc A abcd S abcd O . . . .
T N . . . . C . . E . . . E Ah e
t I ab cd S ab R abc R P
I hf T o r2 R . . . . . . .
- T 1 2 3 4 5 6 7 y@e c* m ,D Tt 's @ g f+ E' h T
,ll
y INSTRUMENTATION
{
SOURCE RANGE MONITORS LIMITING CONDITION FOR OPERATION 3.3.7.6 At least the following source range monitor channels shall be OPERABLE: )
- a. In OPERATIONAL CONDITION 2*, three. {
- b. In OPERATIONAL CONDITIONS 3 and 4, two.
APPLICABILITY: OPERATIONAL CONDITIONS 2*, 3, and 4.
ACTION:
- a. In OPERATIONAL CONDITION 2* with one of the above required source range monitor channels inoperable, restore at least 3 source range monitor channels to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least 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. In OPERATIONAL CONDITION 3 or 4 with one or more of the above required source range monitor channels inoperable, verify all insertable control rods to be inserted in the core and lock the reactor mode switch in the Shutdown position within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. .
l SURVEILLANCE REQUIREMENTS l
4.3.7.6 Each of the above required source range monitor channels shall be (- )l demonstrated OPERABLE by:
- a. Performance of a:
- 1. CHANNEL CHECK at least once per: l a) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in CONDITION 2*, and b) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in CONDITION 3 or 4.
- 2. CHANNEL CALIBRATION ** at least once per 18 months.
- b. Performance of a CHANNEL FUNCTIONAL TEST. 1
- 1. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to moving the reactor mode switch from e the Shutdown position, if not performed within the previous 7 days, and At least once per 31 days. l 2.
- c. Verifying, prior to withdrawal of control rods, that the SRM count rate is et i nst C.7*** cps with the detector fully inserted.
- 2. 3 "With IRM's on range 2 or below.
- Neutron detectors may be excluded from CHANNEL CALIBRATION.
- "revided :igul-t: nei:: r:ti 1: 1 2. Othe ri:0, 2 p:. ,
1%y bs reduced to 2 0.7 cp prodded s{pa!-to- none do is Z A0*
i FERMI - UNIT 2 3/4 3-64 1
REF.UELING OPERATIONS 3/4.9.2 INSTRUMENTATION LIMITING CONDITION FDR OPERATION 3.9.2 At least 2 source range monitor * (SRM) channels shall be OPERABLE and inserted to the normal aperating level with:
- a. Annunciation and continuous visual indication in the control room,
- b. One of the required SRM detectors located in the quadrant where CORE ALTERATIONS are being performed and the other required SRM detector located in an adjacent quadrant, and
- c. Unless adequate shutdown margin has been demonstrated per Specifica-tion 3.1.1, the " shorting links" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn,.
APPLICABILITY: OPERATIONAL CONDITION 5.
ACTION:
With the requirements of the above specification not satisfied, immediately suspend all operations involving CDRE ALTERATIONS and insert all insertable control rods.
SURVEILLANCE ItEQUIREMENTS 4.9.2 Each of the above required SRM channels shall be demonstrated OPERABLE by:
- a. At least once per 12 ' hours:
,_ 1. Performance of a CHANNEL CECK, --
- 2. Verifying the detectors are inserted to the normal operating L / level, and _
- 3. During CORE ALTERATIONS, verifying that the detector of an OPERABLE SRM . channel is located in the core quadrant where CORE I.LTERATIONS are being performed and another is located in an adjacent quadrant.
"The ese of special-movable d:*dr: i: ring C0,95 ^.LTERATIONS in place-oN nomal-4RM-nuclear dete - is-permissible-a: 1r.; :: these-speci:1 detectors-
- : ::=;-c4nd-to-the-nomal-SRM-s4eseits. See Av5 ~'T for ifew bfit ok # -
- Not required for control isds removed per Specifwien 3.9.10.1 and 3.9.10.2.
T l
FERRI - UNIT 2 3/4 9-3
INSERT (PAGE 3/4 9-3) l
- Maintenance of a minimum count rate for these channels is not required when sixteen or fewer fuel assenblies, each of which are )
installed in one of the four' positions directly adjacent to one of j the four permanently installed Sm nuclear detectors (four fuel assemblies surrounding each Sm detector), are in the core. Sm minimum count rate requirements apply for any CORE ALTEFATION I involving any other fuel assembly. The use of special movable detectors during CORE ALTERATIONS in place of the normal Sm detectcrs is permissible as long as these special detectors are connected to the normal Sm circuits, i
i l
l
_ _ - - _ - _ _ _ i
REFUELING OPERATIONS i
SURVEILLANCE REQUIREMENTS (Continued)
- b. Performance of a CHANNEL FUNCTIONAL TEST:
- 1. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the start of CORE ALTERATIONS, and "
- 2. At least once per 7 days.
2:. 3
- c. Verifying that the channel count rate is at 1 ::t 0.'* cps:
- 1. Prior to control rod withdrawal,
- 2. Prior to and at lea t once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during CORE ALTERATIONS, and
- 3. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- d. Verifying, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during, that the RPS circuitry " shorting links" have been removed during the time any control rod is withdrawn ** unless adequate shutdown margin has demonstrated per Specification 3.1.1.
-)
9 "T:r :nly th: f;:1 ::v;;;nt: 7:quir:d t: 7 ;1::: n: tr:n ::: :::, th: ::;nt ret ::g 0.3 :: nt: p;r :::: d pri:r t: ::hi;ving : buri.up :f 2000 lL.,,,50 r:ft::d i:T en the fir,t ::r; pr vid:d th: :ign;i-t: n f;; 7:ti: : 2. ^fter-e burne; ef 2000 "MS/T, the : ent r:t: :::t 5: :t 1;;;t 0.7 :p: pr!vid:d th:
- f;n
- 1-t: n:i:: r:ti: i: ;2. Otherwitt, 3 eps.
- Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.
N See /DSGRT for new fochoh Y j
3/4 9-4 Aceadment No. 1 . -)
l FERMI - UNIT 2 l
r- - . - _ . -. _
l: .
l-1 I
INSERT (PAGE 3/4 9-4)
- May be reduced to 10.7 CPS provided the signal-to-noise ratio is 1 20. Maintenance of a mininum count rate for these channels is not required when sixteen or fewer fuel assenblies, each of which are installed in one of the four positions directly adja::ent to
_one of the four permanently installed Sm nuclear detectors (four fuel assenblies surrounding each SIN detector), are in the core.
Sm mininum count rate requirements apply for any CORE ALTEPATION involving any other fuel assembly.
1
'l i
\
l l
l
- ~
F;,'
1r
.= ,. 1
.\
b 3/4.9 ' REFUELING OPERATIONS BASES 3/4.9.1 REACTOR MODE-SWITCH Locking the OPERABLE reactor mo'de switch in the Shutdown or Refuel position, as specified, ensures that the restrictions on control rod withdrawal and' refueling platform movement during the refueling operations are properly activated. These conditions reinforce the refueling procedures and reduce the probability of inadvertent criticality, damage to reactor internals or fuel assemblies, and exposure of personnel to excessive radioactivity.
3/4.9.5 INSTRUMENTATION 5ec B.4se3 joue ef The OPERA 0!LITY cf at least tw; source range monitoes-ensures-that-redundant 2: nit:rin; ::p:bflity i: vcilcb1: t: detect ch:nge: in the rc::titity cendition Of th: ::re.
3/4.9.3 CONTROL R0D POSITION The requirement that all control rein be inserted during other CORE ALTERATIONS ensures that fuel will not be loaded into a cell without a control rod.
{
3/4.9.4 DECAY TIME The minimum requirement for reactor subcriticality prior to fuel movement ensures'that sufficient time has elapsed to allow the radioactive decay of the short lived fission products. This dechy time is consistent with the assump-tions used in the accident analyses.
3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during movement of fuel within the reactor pressure vessel.
r (
FERMI - UNIT 2 B 3/4 9-1
l .
l "4 -
I l ..
1 .
INSERT (BASES) I i
)
The OPERABILITY of at least two source range nonitors, one loc'3ted in the quadrant where CORE ALTERATIONS are being performed and the other located in an adjacent quadrant, ensures reactivity nonitoring l capability is available to detect changes in the reactivity condition of the core. The Sm in the adjacent quadrant provides a back-up to )j the SM in the quadrant where CORE ALTERATIONS are being performed whenever a continuous multiplying medium exists between the location j of CORE ALTERATIONS and the Sm. The mininum count rate is not '
required when sixteen or fewer fuel assemblies, each directly adjacent to a permanently installed Sm nuclear detector, are in the core.
This provision allows complete core unloading without the use of .)
special movable detectors. During core re-loading up to four ,
irradiated fuel assemblies are placed next to each SM4 detector to l produce greater than the mininum count rate. Fuel loading patterns i are chosen such that each set of contiguous fuel assemblies surrounds )
at least one SR4 detector. This ensures a continuous multiplying ]
medium is established between at least one Sm detector and the !
location of CORE ALTERATIONS thus enhancing the ability of the Sms to respond to any abnormal reactivity increase. ;
i l
i l
.. _ _ _ _ _ _ _ - _ . I