ML20077M475
| ML20077M475 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 08/01/1991 |
| From: | UNION ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20077M470 | List: |
| References | |
| ULNRC-2451, NUDOCS 9108130368 | |
| Download: ML20077M475 (17) | |
Text
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ATTACHMENT 1 DESCRIPTION.OF-PROPOSED CHANGES TO TECllNfCAL SPEC 1FICATIONS ,
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I 9108130368 910801 .
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, - UlJIRC-2451 Attachment 1-E
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'0ESCRiffl0N OF fROF0 SED CHANGES TO TECliNICAl,'STEctFICATIONS i
t ltes_NA g_ SectionNur}er ,fection Title Description of Change 1 3.3.3.6 Instrerentation/ Accident Monitoring ' Typographic change of singular instrumentation /Liriting Condition
- monitor" to plural "ronitors " .
for Operation 2 Table 3.3-4 Engineered Safety Features Values for item 8.a should be "83V" Actuation Syster Instrumentation and "83'O.-8.3Y" as issued in Nff 30 -
- Trip Setroints ratherthan"!)3Y"and")74'JY"as issued in KRC letter dated 11/1/64.
3 Table 3.3 10 Accident Manitoring instrumentation item 15 should be descrited as !
- Containt.cnt Norral Surp Water Level" indicators to distinguish them from tna recirculation surp level indicators.
Instrument identification numbers are added to !tems 16 and 18.
4' . I3.6.4.1 Centainment Systems / Combustible Gas I,crs restrictive Tech Srec 3.6.4.1 is Control /ltydrogen Analyzers / Limiting made consistent with sore restrictive Condition for Operation Tech Spec 3.3.3.6.
5- 4.11,2.5- Fadioactive Effluents /Erplosive Gas Editorial change to remove reference to Nixture/ Surveillance Requirer:ents Table 3.3-13. This r terence was removed l'y previous amendment rep ert (Rett ULNRC4070. 9/6/A9) tiut ten was not revised during amendment preparation Omendment 50).
'6 ' 6.2.2 Administrative Controls / Editorial change to remove reference to Organization /llnit Staff. Assistant Superintendent. Operations.
This position is to be deleted effective 6/1/91.
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, ULNRC-2451 E
ATTACHMENT 2 TECHNICAL SPECIFICATION CilANGES .
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REVISlon 2 .
INSTRUMENTATION
't ACCIDENT HONITORING INSTRJHENTATION LIMITING CONDITION FOR OPERATION The accident monitoring instrucentation channels shown in Table 3.3.3.6 3.3-10 shall be OPERABLE.
APPLICABILITY: HODES li 2, and 3.
ACTION:
a.
With the number of OPERABLE accident monitoring instrumentation channels less than the Total Numect of Channels 7 days; otherwise, be in at least HOT STANDBY within the next 6 hou .
t and in HOT SHVTDOWN within the fo11 ewing 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
. E5 b.
With the number of OPERABLE accident monitoring instrumenta channels, except'the containment radiation level mecite?"and the u vent - high range noble ga's monitor, less than the Minimum Channe '
OPERABLE requirements of Table 3.3'10, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> the following.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ,'
- c. With the number of OPERABLE channels for 0theless level ;; nit;r or the unit vent - high range noble gas monitor containm rAo6;lors k than the Minimum Channels OPERABLE requirements of Table 3.3-1. ,
initiate the preplanned alternate eethod of monitoring the appropriate l parameter (s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and either restore the inoperable chan to OPERABLE status within 7 days, or prepare and submit a Special ,_
Report to the Commission pursuant to Specifica ~
plans and schedule for restoring the channels to CPERABLE status.
- d. The provisions of Specification 3.0.4 are not applicable.
a SURVEILLANCE REQUIREHENTS
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4.3.3.6 Each accident monitoring instrumentation channel shall be demons OPERABLE by performance of the CHANNEL CHECX and CHANNEL CAL .
frequencies shown in Table 4.3-7.
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3/4 3-52 .<:
CALLAWAY - UNIT 1 --
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t M LE 3.3-4 (Continued) 1 n g M ENGINEERED SAFETY FEATURES ALTUATION SYSTfH INSTRUMENTATION TRIP SETPOINTS i
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- TOTAL SENSOR TRIP ALLOVADLE
' Z ERROR (S) SETPOINT VALUE FUNCTIONAL UNIT Alt 0VANCE (TA) _
b 6. Auxiliary Feedwater (Continueri) '
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- ' e. Safety Injection-Start Hotor-Driven See Item 1. above far all Safety Injection Trip setpoints and Allowable Values.
Pumps
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. f. Loss-of-Of fsite Power- !
- Start Turbine-Driven H.A. H.A. H.A.
- Pump N.A.
H. A. l
- g. Trip of All Main Feedwater Pumoc-w
) Start Motor-Driven H.A. H.A. N.A.
- Pumps H.A. H.A. ,
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- h. Auxiliary Feedwater .
Pump Suction Pressure- >21.71 psia >20.64-psia -
H. A. H.A. H.A.
Low (Transfer to E5W) l
- 7. Automatic .iwitchover j to Containmeret Sump i
- a. Autonatic Actuation I Logic and Actuation N.A. N.A. r l Relays (SSPS) H.A. H.A. H.A. .
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- b. 3.4 1.21 2.0 ->36% ~>35.2%
RWST Level-Low-Low coincident with Co l
Safety Injection See. Item 1. above for Safety Injection Trip Setpoints and Allowable Values. --
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- 8. Loss of Power yV S3+ 0, - 8,3 V l
- a. 4 kV Undervoltage N !
-Loss of Voltage H.A. N.A. H.A. p (120V Dus) +74-P (1 ROV Dus) w/1s delay w7140.2,-0.5s delay l
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TADtE 3.3-10 1
TATION n ACCIDENT MONITORING INSTRisitC: tilNIMUM TOTAL N CilANNELS g HO. OF OPERABLE
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. lH5TRUMENT_ 1 2 -1 E 1. Containment Pressure
- a. Normal Range ,
2 1
~l C Extended Range 2 1
~ b. de Range) -
- 2. Reactor Coolant Outlet Temperature - Tl!OT d N'"9"
- 3. Reactor Coolant Inlet Temperature - T COLD 2 1
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- 4. Reactor Coolant Pressure - Vide Range 2
- 1/ steam generator 2/ steam generator f
- 5. Pressurizer Water Level 1/ steam generator 1/ steam generato'r
- 6. Steam Line Pressure .larrow Range ,
1/ steam generator 1/ steam generator ,
- 7. " Steam Generator Water Level 1
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- 8. Steam Generator Water Level - Wide Range f 2
y Refueling Water Storage Tank Water Level 2 1 '
$ 9. 1/ steam generator f Containment. Ilydrogen Concentrat. ion Level 1/ steam generator
- 10. 1/ Valve
- 11. Auxillary Feedwater flow Rate 1/ Valve 1/ Valve
- 12. PORV Position Indicator * - 1/ Valve e 1/ Valve i
- 13. PORV Block Valve Position Indicator ** ^ 1/ Valve ,
1 Safet ValvQ@..@'icat o r=damalSunf 2 14.
1 Containment9 dater Level N. A. a
- 15. . Gr-Ric- 69,- 60) 2/ core quadrant Containment Radiation Level (Iligh Range 4/ core quadrant 16.
N.A.
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- 17. Thermacouple/ Core Cooling Detection System (Gf-R(C- 216) CO -
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Unit Vent - liigh Range Noble Gas Monito . -
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9 CONTAINMENT SYSTEMS
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3/4.6.4 COMBUST 1BLE CAS CONTROL HYDFOGEN ANALYZERS
- LIMITING CONDITION FOR OPERATION
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3.6.4.1.Two independent containment hydrogen.analy:ers shall be OPERABLE.
APP'LICABILITY: gE 2j 6 d b ACTION: -
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- a. With one containment hydrogen analyzer inoperable, restere the. 7 '
inoperable analyzer to OPERABLE status within *<?fTays or be in at
- least u>i din HOT6 0 STA[NDBY oll0Wiq (o kot1($ within , the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; ud Hor SHuTboWN
- b. With both hydrogen an'11yzers inoperable. restore 'at least one - g analyzer to OPERABLE status within. W hours or be in at least HOT STANDBY within the next 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />sy awf Hop ,$Horgowg gj$,'g ke hll0WlQ b bottfS, i
c SURVEILLANCE REOUIREMENTS 4.6.4.1 .Each containment hydrogen analyzer shall be demonstrated OPERABLE by l
i the performance of an ANALOG CHANNEL OPERATIONAL TEST at least once per 31 days, i and at least once per 31 days on a STAGGERED TEST BASIS by performing a CHANNEL i CALIBRATICH using sample gas containing' ten volume percent hydrogen, balance nitrogen. -
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n CALLAWAY - UNIT 1 3/4 6-31 l.
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-t 3010 ACTIVE EFFLUENTS ,
EXP(051VE GAS MIITURE 7
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3 iMITING CONDITION FOR OPEPATION
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l 3.11.2.5 The concentration of oxygen in the VASTE GAS HOLD'JP SYSTEM shNil be
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i limited to less than or equal to 3% by volume whenever the hydrogen concentra-t' ion exceeds 4% by volume, y L s m.
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APPLICABILITY: At all times. Nd 5I ACTION:
- a. With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM M :._ greater than 3% by volume but less than or equal to 4 by volume, n;g -j rMuce the cxygen concentration to the above limits within 43 hours.
- b. With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM 1.)-24 }
=r =s & greater than at by volume and the hydrogen concentration greater .
@_ m than 41 by volume, irmediately suspend all additions of waste gases "LEIGi T to .the systt:m and reduce the concentratien of oxygen to less than
;G 2 E er equal to 4 by volume, then take ACTION a. above.
?E a 4- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
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-b ? 4.11.2.5 The concentrations of hydrogen and oxygen in the WASTE GAS HOLDUP l
-fMJ _A 1-liSTEM shall be determined to be within the above limits by continucusly d:gtg i Mi e aitoring the waste gases in the WASTE GAS HOLDUP SYSTEM with the hydrogen l SMist d a.c oxygen monitors re;uired CPERABLE by 4cb h 2.: ': # Specification ifE W in 3.3.3.10.
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@- h9 iP ,ULLAWAY - UNIT 1 3/4 11-2 Amenchent No. 37, 50 t
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w l J! j 9 - 3e ADMINISTPATIVE CONTROLS 5.2 ORGANIZATION (Continued) F 3 y UNIT STAFF - [ .' 6.2.2 The Unit organization shall be subject to the following: Un gy
- a , a. Each on duty shift shall be. composed of at least the minimum shif t
] crew composition shown in Table 6.2-1; d b. At least one licensed Operator shall be in the control room when y fuel is in the reactor. In addition, while the unit is in MODE 1
+ 2, 3 or 4, at least:ene licensed Senior Operator shall be in the '.
control room; - 7*i?k ,;r g g .. -
- c. An individual from the Health Physics orgar,izationi, qualified in
- b. = . radiation protection procedures, shall be on site when fuel is in
. gi the reactor;
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I'~$ 1. d. All CORE ALTEPATIO:..i shall be observed and directly supervised by
% *' either a licensed Senior Operator or licensed Senior Operator L ~.a c- Limited to Fuel Handling who has no other concurrent responsibil-w , ities during this operation; i.
f~ e. A site Fire Brigade of at least five membersi shall be maintained m, onsite at all times. The Fire Brigade shall not include the Shif t t *- Supervisor, and the two other members of the minimum shif t crew
-M necessary for safe shutdown of the unit and uy personnel required -
WR_, for other essential functions du.-ing a fire emergen;y; P?O f.
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Administrative procedures shall be developed and implemented to
- limit the ecorking hours of unit staff who perform safety-related functions; e.g., licensed Senior Operators, licensed Operators, '
I ~,j- health physics personnel, equipment operators, and key maintenance i _ personnel,
^. the amount of overtime worked by Unit staff trembers performing
- safety-related functions shall be limited in accordance with the l g"2 '
.: hRC Policy Statement on working hours (Generic Letter No. 82-12); l
; 9 The Superintendent, Operations,.or the- Assisteni. L g in w.deat,
^ ^ - " " Shift Supervisors, and Operating Supervisors shall hold a senior reactor operator license. The Unit Reactor Operator shall hold a reactor operator license or a senior reactor operator license.
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fHay be less than the minimum requirements for a period of time not to exceed 1 l
? 2 hours in order to accommodate unexpected absence provided iranediate action
. 15 taken to fill the required positions. '
E llAWAY - UNIT 1 6-2 Amendment No. 37
ULNRC-2451 ATTACHMENT 3 SAFETY EVALUATION
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ULNRC- 2451 Attachment 3 Page 1 of 3 i M FETy EVA_LUATION Thic amendment application requests revisions to various Technical Specificatiens described in Attachment 1. The proposed changes to the Technical Specifications do not involve an unreviewed safety question because operation of the Callaway Plant with this change would not
- 1) Increase the probability of occurrence or consequences of an accident or malfunction of equipment important to safety previously e"aluated in the safety analysis rnport,
- 2) Create the possibili ty f or an accident or malfunction of a different type than any previously evaluated in the safety analysis report, or
- 3) Reduce the margin of safety as defined in the basis for any technical specification.
Specifically, for each item listed in Attachment 1: Item Ngz_1 The typographic change of the singular " monitor" to the plu al " monitors" merely corrects a typographical error. The change does not impact the reliability or availability of plant equipment The change does not alter the function or capabilities of existing plant equipment. There is no new type of accident or malfunction being created, and the method and manner of plant operation is unchanged. The chance does not involve plant design changen and does not change any system acceptance criterion. I terrLNo _ 2 The changes described for item 8.a of Table 3.3-4 correctly reflect the values as issued in NPF-30 rather than the incorrect values as issued in NRC letter dated 11/1/84. The changes merely make minor editorial revisions to the text and provide consistency and clarity to the operators which will help avoid operator confusion. The changes do not impact the reliability or availability of plant equipment. The changes do not alter the function or capabilities of existing plant equipment. There is no new type of accident or malfunction being created, and the method and manner of plant operation is unchanged. The changes do not involve plant design changes and do not chance any system acceptance criterion.
i ULNRC- 2451
-Attachmentu3 Page-2.of 3 4
Jtem_Ngz 3 .
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The' changes described for items 15, 16, and 38 of Table
. 3.3-10 are'merely minor editorial revisionsito-the text-and provide - consi stency and clarity to the operators which will help
- avoid' operator confusion. The changes do-not impact the-reliability or' availability of plant equipment The changes do not alter the function or capabilities of existing plant equipment. There is no new type of accident or malfunction being created, and the method and manner of plant operation is unchanged. The changes do not involve plant design changes and #
- do not change f any system acceptance criterion. .
Item No. 4 The change to less rertrictive Tech Spec 3.6.4.1 merely makes an editorial change to be consistent with the more , restrictive Tech Spec 3_.3.3.6. This change _provides consistency-and. clarity to the operators which will. help avoid operator confusion. The changes do not impact the reliability or availability of plant equipment. The changes do not alter the function or capabilities of existing plant equipment. There is. no new type of accident or malfunction being created, and the method _and manner of plant operation is unchanged. The changes
- do not' involve-plant design changes and do not change any system acceptance criterion.
t Item No. 5 l l This change removes reference to Table 3.3-13 which was
- removed by previous amendment request (Ref: ULNRC-2070, 9/6/89),
but-the text was not revised during amendment preparation (Amendment-50). Thia ~ change merely corrects a typographical error. The change does not impact the reliability or
- availabili ty of plant equipment. The change does not alter the
- function or capabilities of_ existing plant equipment, There is no-new type of accident or malfunction being crnated, and the i . mothod_ and manner of plant oporation is unchanged. The change
- does not involve plant design changea and does not change any .
l-system acceptance criterion. t h- _ I_ tem No. 6 This change merely temoves the reference to Assistant
. Superintendent,_Cporations which is to-be deleted effective 6/1/91. This change in merely a minor editorial revision, and does not impact the- reliability or availability of plant
- equipment. The change does not alter the function or capabilities of existing plant equipment. There is no new type i of accident or malfunction being created, and the method and i manner of plant operation is unchanged. The change does not involve plant design changes and does not change any system acceptance critorion.
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ULNRC- 2451 Attachment 3 I' age 3 o f 3 Given the above discuentons, as wel1 as those presented in the'Significant Hazards Evaluation, the proposed changen do not adversely affect or endanger the health or safoty of the general public or involve a eignificant nafety hazard. l 0
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ULNRC- 2451 i ATTACIIMENT 4 SIGNIFICANT HAZARDS EVALUATION
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ULNRC- 2451 +
.g. Attachment'4 -
Page-1-of 2 i S I GN I F I CA1]I'llAZ ARD S_EVALUAT I ON This-_ amendment application requests revisions to various technical specifications described in Attachment'1. l
-The proposed changes do not involve a significant hazards consideration because operation of the Callaway_ Plant with these changes would not:
- 1. Involve a significant_ increase in the probability-or-consequences of an accident previously evaluated,
- 2. Create the possibility of a new or different kind of accident f rom any previously evaluated, or p
l 3. Involve a - significant reduetion in margin of safety. Specifically, for _ each item listed in Attachment 1: Item No. l' The typographic change of the singular " monitor" to the plural " monitors" merely corrects a typographical error. The change does not impact the reliability or-availability of plant equipment. The change does not alter the function or capabilities of cnisting plant equipment. There is no new type of accident or malfunction being created,-and the method and manner pf plant operation is unchanged. The change does not involve ~ plant design changes and does not change any system acceptance criterion. , . Item No. 2 The changes described for item 8.a of. Table 3.3-4 correctly reflect the values as 1esued' 1n NPF-30 rather than the -incorrect values as issued in NRC letter dated 11/1/84. The changes merely make minor. editorial revisions to the text an< provide consistency and clarity-to the operators which will-help-avoid operator confusion. The changes do not impact the reliability or-availability of plant equipment. The changes do not-alter the function or capabilities of existing plant equipment. There is no new type of accident or malfunction being created, and the methodiand manner of plant operation is unchanged. The changes do not involve plant-design changes and do not change any system acceptance criterion. 1 tem _Np, 3 The changes described for items 15, 16, and 18 of Table
~3.3-10 are merely minor editorial revisions to the text and provide consistency and clarity to the operators which will help :
avoid operator confusion. The changes do act impact the reliability or availability of plant equipment. The changes do
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UhNRC- 2453 Attachment 4 Page 2 of 2 not alter the equipment. function or capabili There is no new type created, ties of existing plant unchanged.and Thethe method and manner do not change changes do not ofofaccident plant operation or malfunction is e ng b i any system acceptance involve plant design cha Item _NE.4 cri t eri on. nges and The change makes to less tive Tech Spec 3.3.3,6an editorial clarity to . to be changerestrictive.1Tech Spec 3.6 4 the The changes do opetators not impact This which change will help provides a consiconsistent restric- with the more plant equipment. the stency and The changesre)1abi1i tythe or avai1 ability ofvoid operator con capabilition do not alter of existing plant equipment function or ( of accident or malfunction bei manner There is no { invo.lve plantof p1 ant operation is unchanng created,. ged. and the method andnew type \ acceptance cri terion. design changes and de The changes do not \ not change any system L .I_t e m _ N o . 5 This change removes but the by previous amendment removed reference requent to Table (Ref: durin3.3-13 which was (Amendment error. 50). text was not revised UhMRC-2070, The change does not impact thThis change merely correctsg a availability of plant equipment Thee reliability ora typographical function or capabilities of . method and mannerexisting of cplant plantoperno equipmentchange new type There is does ofnot alter the accident o does systemnot involve plant design changes acceptance ation is unchanged.on being and thecreated,. criterion. The and does not changechange any
. Item No._6 This Superintendent. change merely removes the This impact change is merely the reliability or a minororial editOpera tiens which i s reference to Assint to be deleted effectiva 6 revision, plant equipment. There change d.oes not alter the functiavailability of pinnt t being created, is no new typeon or capabilities of existing The unchanged.
does not change Theanychange system doen not of involvand accident themalfunction or plant operation method is and manner of As discussed above, acceptance criterion.e plant desian changes and significant increase the proposed changes do not or different kind ofaccidnnt in the probability previously or evaluated involve a or create tho consequences of an proposed margin changes do not resultaccident from possibility of a new safety. in a any signi previously fi can t evaluated . The proposed changes do notTherefore, i t han consideration. involve a been determinedreduction that tha in a signi ficant hazarda
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