ML20151X866
| ML20151X866 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 08/19/1988 |
| From: | SYSTEM ENERGY RESOURCES, INC. |
| To: | |
| Shared Package | |
| ML20151X856 | List: |
| References | |
| GL-87-09, GL-87-9, NUDOCS 8808260127 | |
| Download: ML20151X866 (64) | |
Text
{{#Wiki_filter:. . P39 NL 88-01 l 4 1 kiji . 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1_ Compliance with the Limiting Conditions for Operation contained in the succeeding Specifications is required during the OPERATIONAL CONDITIONS or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met. 3.0.2 Noncompliance with a Specification shall exist when the requirementr of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals. If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the Action requirements is not required. 3.0.3 When a limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in an OPERATIONAL CONDITION in which the Specification does not a'pply by placing it, as applicable, in:
- 1. At least STAP. TUP within the next 6 hours,
- 2. At least HOT SHUT 00WN within the following 6 hours, and
- 3. At least COLD SHUT 00WN within the subsequent 24 hours.
Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time A limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the individual Speci-fications. ' This specification is not applicable in OPERATIONAL CONDITION 4 or 5. 3.0.A Entry inte er OPEr.ATIOuAL COM0!TIOM er othe specified condition shall act be =ede unless the conditions fee the Limiting Condi+ica fe- Operatica are met "ithout reliance er previcient centained 4a the ^.CTIOu 7 quiree:7t , nj
-previsica shal' not prevent pas: ge through er te OPER"!OP^L COMDITIONS ::
required te comp!y uith ^.CTIOP requirements. Exception: te the:0 requircrent: cre stated 4^ the indi"idual Speci#icati:nc. INSERT A 88082601{$$$$N16 PDR ADO PDC P GRAND GULF-UNIT 1 3/4 0-1 NO ' -
N L. 88-of Ffo APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillaace Requirements shall be met during the OPERATIONAL CONDITIONS l or other conditions specified for individual Limiting Conditions for Operation I unless otherwise stated in an individual Surveillance Requirement. l 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:
- a. A maximum allowable extension not to exceed 25% of the surveillance interval, but
- b. The combined time interval for any 3 consecutive surveillance intervals !
INSERT B shall not exceed 3.25 times the specified surveillance interval. A.O.? c flere te perfer- 2 Surve!' lance Requirereat withia +he speciriad +4=a 1 Intocusi chs11 rnne+4tuta s f s t le nca +^ maat thn f10CDAQTtTTV -aan.4ea-an+c #^n s Lf-Ih'EgCEEiftIEE#EE'5h:E:kIE 'EEch5IEnE5c'hEEEE'EEkufbESEEhE5-EskEk5'- E the i-divide:1 Speci'ic: ten:, Surve!'! ne requircrent: de not %ve te be m e s s_ i. e. om,4.- .,+_
-,,...,aa - - - mm. 4 m mr-. - - -
7 ... 7 4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within_tb3_ _ applicable surveillance interval or as otherwise specified. 4 [IN5EiTlC) l 4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, & 3 components shall be applicable as follows:
- a. Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 1 pumps and valves shall be performed in accordance with Section,XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)
(6) (1).
- b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities requirt.:d by the ASME Soiler and Pressut e Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology for inservice inspection and testing inspection and testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days GRAND GULF s 1 3/4 0-2 Amomr %, _,
M L '31 -ol P41 INSERT A 3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall not be made when the conditions for the Limiting Conditions for Operation are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval. Entry into an OPERATIONAL CONDifION or specified condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. INSERT B 4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours. INSERT C This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements. J16 MISC 88080201 - 2
F42. NL Bb-oI REACTIVITY CONTROL SYSTEMS LIMITING CONDITNN FOR OPERATI5N (Continued)
~ '
' ACTION (Continued) i
- 2. If the inoperable control rod (s) is inserted, within one hour disare the associated directional control valves *" either:
a) Electrically, or b) H.craulically by closing the drive water and exhaust water itolation valves. Otherwise, be in at least HOT SHUTDOW within the next 12 hours.
--O. The ,,,iv ieiwns ef Specificetiec 0.0.4 ere i.et epplicet,h.
l
- c. With more than 8 control rods inoperable, be in at least HOT SHUTDOW' within 12 hours.
d. With one scram discharge volume vent valve and/or one scram discharge voluna drain valve inoperable and open, restore the inoperable valve (s) to theOPERABLE next 12 hours, status within 24 hours or be in at least HOT SHUTDOW within e. With two scram discharge volume vent valves and/or two scram discharge volume drain valves inoperable and open, restore one valve in the vent line and one valve in the drain line to OPERABLE status within 8 hours and restore all valves to OPERABLE status within the next 16 hours or close at least one vent valve and one drain valve and be in a least HOT SHUT 00W within the next 12 hours. f. With any scram discharge volume vent valve (s) and/or any scram discharge volume drain valve (s) inoperable and closed except when required by ACTIOh statement e. above, restore all valves to OPERABLE status within ( 8 hours or be in at least HOT SHUTDOW within the next 12 hours. SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The scram discharge volume drain and vent valves shall be demonstrated OPERABLE by:
- a. At least once per 31 days verifying each valve to be open,* and
- b. At least once per 92 days cycling each valve through at least one complete cycle of full travel.
"These valves may be closed intermittently for testing under administrative controls.
**May be reareed intermittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.
GRAND GULF-UNIT 1 3/4 1-4 - Amendment No. 21,- Effe: W : Sata: C2 2 * "
- F'43 hL $6-cl REACTIVITY CONTROL SYSTEMS k hj LIMITING CONDITION FOR OPERATION (Continued)
ACTION: (Continued)
- b. With a "slow" control rod (s) not satisfying ACTION a.1, above:
- 1. Declare the "slow" control rod (s) inoperable, and
- 2. Perform the Surveillance Requirements of Specification 4.1.3.2.c at least once per 60 days when operation is continued with three or more "slow" control rods declared inoperable.
Otherwise, be in at least HOT SHUTDOWN within 12 hours.
- c. With the maximum scram insertion time of one or more control rods exceed-ing the maximum scram insertion time limits of Specificatica 3.1.3.2 as determined by Specification 4.1.3.2.c, operation may continue provided that:
- 1. "Slow" control rods, i.e. , those which exceed the limits of Specifi-cation 3.1.3.2, do not make up more than 20% of the 10% sample of con-trol rods tested.
- 2. Each of these "slow" control rods satisfies the limits of AC1 ION a.1,
- 3. The eight adjacent control rods surrounding each "slow" control rod are:
a) Demonstrated through measurement within 12 hours to satisfy the maximum scram insertion time limits of Specification 3.1.3.2, and (' 4. b) OPERABLE. The total number of "slow" control rods, as determined by Specifica-tion 4.1.3.2.c, when added to the sum of ACTION a.3, as determined by Specification 4.1.3.2.a and b, does not exceed 7. Otherwise, be in et least HOT SHUTDOWN within 12 hours.
- d. The previtten: Of Sp::ific:ticr 3.0.1 :r: net :pplic:ble.
3 SURVEILLANCE REQUIREMENTS 4.1.3.2 The maximum insertion time of the control rods shall be demonstrated
- through measurement with reactor coolant pressure greater than or equal to 950 psig and, during single control rod scram time tests, the control rod drive pumps isolated from the accumulators:
- a. For all control rods prior to THERMAL POWER exceeding 40% of RATED THERMAL POWER following CORE ALTERATIONS
- or after a reactor shutdown that is greater than 120 days,
- b. For specifically affected individual control rods ** following mainten-ance on or modi #ication to the control rod or control rod drive system ,
which could affect the scram insertion time of those specific control rods, and
- c. For at least 10% of the control rods, on a rotating basis, at least once per 120 days of POWER OPERATION.
^Except normal control rod movement.
('
**The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 2 provided this surveillance is completed prior to I entry into OPERATIONAL CONDITION 1.
GRAND GULF-UNIT 1 3/4 1-7 Amendment No.35, - l l
644 NL 88 05 REACTIVITY CONTROL SYSTEMS CONTROL R00 SCRAM ACCUMULATORS LIMITING CONDITION FOR OPERATION 3.1.3.3 All control rod scram accumulators shri t be OPERABLE: APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 a _" 6*. ACTION:
- a. In OPERATIONAL CONDITIONS I and 2:
- 1. With one control rod scram accumulator inoperable, within 8 hours:
a) Restore the inoperable accumulator to OPERABLE status, or b) Declare the control rod associated with the inoperable accumulator inoperable. Otherwise, be in at least HOT SHUTOOWN within the next 12 hours. 2.
~
With more than one control rod scram accumulator inoperable, deci .re the associated control rods inoperable and: a) If the control rod associated with any inoperable scram accumulator is withdrawn, immediately verify that at least one control rod drive pump is operating by inserting at least one withdrawn control rod at least one notch or place the reactor mode switch in the Shutdown position.. b) Insert the inoperable control rods and disarm the associated directional control valves either:
- 1) Electrically, or
- 2) Hydraulically by closing the drive water and exhaust water isolation valves.
Otherwise, be in at least HOT SHUTDOWN within 12 hours. a
- b. In OPERATIONAL CONDITION 5*: of 8
- 1. With one withdrawn control rod with its associated scram accumulator inoperable, insert the affected control rod and 5 disarm the associated directional control valves within one j hour, either: 8 a) Electrically, or E
b) Hydraulically by closing the drive water and exhaust water isolation valves. ]
- 2. With more than one withdrawn control rod with the associated -}2 scram accumulator inoperable or with no control rod drive pump "
operating, immediately place the reactor mode swJtch_in the_ _ Shutdown position. @ P!09Q pdy- --
, m . m u. e ,4. m. m..,. m..< e 7- m. . 4. < 4. ,114. . -. s,n,.4
..,- - - + - - ,774. ,. . w. ,. r. -
. T s. . 7 Not "At least the accumulator associated with each withdrawn control rod.
applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
~
GRAND GULF-UNIT'1 3/41-8 (Amendmen} [o[ _ ] _
o . P45 INSERT
- c. With one or more accumulator pressure detector or alarm inoperable, '
verify accumulator pressure to be > 1520 psig at least once per 24 hours, or declare tha associated accumulator inoperable. With one or more accumulator leak detector or alarm inoperable, verify Od+ accumulated water drained at least sne per 48 hours, or declare the l associated accumulator inoperable. , I l l l I l l I I J14 MISC 880707 - 1
- p%
ML 68 oi REACTIVITY CONTROL SYSTEMS CONTROL R00 DRIVE COUPLING LIMITING CON 0! TION FOR OPERATION 3.1.3.4 All control rods shall be coupled to their drive mechanisms. APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 5*. ACTION:
- a. In OPERATIONAL CONDITION 1 and 2 with one control rod not coupled to its .
- associated drive mechanism, within 2 hours:
- 1. If permitted by the RPCS, insert the control rod drive mechanism to accomplish recoupling and verify recoupling by vithdrawing the control rod, and:
a) Observing any indicated response of the nuclear instrumentation, and f b) Demonstrating that the control rod will not go to the overtravel i position.
- 2. If recoupling is not accomplished on the f,irst attempt or, if not permitted by the RPCS, then until permitted by the RPCS, declare the control rod inoperable, insert the control rod, and disarm the associated directional control valves ** either:
a) Electrically, or b) Hydraulically by closing the drive water and exhaust water isolation valves. Otherwise, be in at least HOT SHUT 00WN within the next 12 hours,
- b. In OPERATIONAL CONDITION 5* with a withdrawn control rod not coupled to its associated drive mechanism, within 2 hours either:
- 1. Insert the control rod to accomplish recoupling and verify recoupling by withdrawing the control rod and demonstrating that the control rod will not go to the overtravel position, or
- 2. If recoupling is not accomplished, insert the control rod and disarm the associated directional control valves ** either:
a) Electrically, or b) Hydraulically by closing the drive water and exhaust water isolation valves.
- c. The previ:icn: ef Spe:f'f:: tier 3.0.' :re net Up!! cele.
At least each withdrawn control rod. Not applicable to control rods removed 1 per Specification 3.9.10.1 or 3.9.10.2. na May be rearmed intermittently, under administrative control, to permit testing associated with restoring the contr'ol rod to OPERABLE status. GRAND GULF-UNIT 1 3/4 1-10 blHtMOn do.
P4'? ML SS -ot REACTIVITY CONTROL SYSTEMS CONTROL R00 POSITION INDICATION LIMITING CONDITION FOR OPERATION 3.1.3.5 At lea'st one control rod position indication system shall be OPERABLE. APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 5*. ACTION:
- a. In OPERATIONAL CONDITION 1 or 2 with one or more control rod position indicators inoperable, within one hour:
- 1. -Determine the position of the control rod by the alternate control rod position indicator, or
- 2. Move the control rod to a position with an OPERABLE position indicator, or
!. 3 When THERMAL POWER is:
a) Within the low power setpoint of the RPCS:
- 1) Declare the control rod inoperable, and
- 2) Verify the position and bypassing of control rods with inoperable "Full-in" and/or "Full-out" position indicators by a second licensed operator or other technically qualified members of the unit technical staff.
b) Greater than the low power setpoint of the RPCS, declare the control rod inoperable, insert the control rod, and disarm the associated directional control valves ** either:
- 1) Electrically, or
- 2) Hydraulically by closing the drive water and exhaust water isolation valves.
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours. *
- b. In OPERATIONAL CONDITION 5* with both control rod position indicators for a withdrawn control rod inoperable, move the control rod to a position with an OPERABLE position indicator or insert the control rod.
- c. The previcien: ef Sp::tficati:n 3.0.' cr: n:t oppif edk.
"At least each withdrawn control rod. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
**May be rearmed intermittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.
t GRAND GULF-UNIT 1 3/4 1-12 AtACNoK D K No.
P48 NL 63 -01
. , . g. 3/4.3 INSTRUMENTATION
- 6., ;
3 /_4. 3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME'as shown in Table 3.3.1-2. APPLICABILITY: As shown in Table 3.3.1-1. ACTION:
- a. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel and/or that trip system in the tripped conditior*
within one hour. -The provi:10: Of Speci'icatier 3.0.d are net applicable,
- b. With the number of OPERABLE char.nels less than required by the Minimum OPERABLE' Channels per Trip System requirement for both trip system;, place at least one trip system ** in the tripped condition within one hour and take the ACTION required by Table 3.3.1-1.
SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1.1-1. 'x
\
4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated eatomatic operation of all channels shall be performed at least once per 18 months. 4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one chan-nel per trip system such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip system.
*An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours or the ACTION required by Table 3.3.1-1 for that Trip Function shall be taken, t
**The trip system need not be placed in the tripped condition if this would cause the Trip Function to occur. When a 1-ip system can be placed in the tripped condition without causing the Trip Function to occur, place the trip system with the most inoperable channels in the tripped condition; if N% both systems have the same number of inoperable channels, place either trip system in the tripped condition.
GRAND GULF-UNIT 1 3/4 3-1 gmy go, _
- Nt. 'SS -ol Wi INSTRUMENTATION
- \ $.
g' 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATI,0N
? :
LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3. APPLICABILITY: As shown in Table 3.3.2-1. ACTION:
- a. With an isolation actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
- b. With the number of OPERABLE channels less than required by the Minimum
.i OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel (s)'*and/or that trip system in the tripped condition
- within one hour. -The provi:icn; Of Speci'ic: tier 3.0.A -
- rc not appliceble.
- c. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems,
~( place at least one trip system ** in the tripped condition within one hour and take the ACTION required by Table 3.3.2-1.
SURVEILLANCE RE0VIREMENTS 4.3.2.1 Each isolation actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.2.1-1. . 4.3.2.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months. c 4.3.2.3 The ISOLATION SYSTEM RESPONSE TIME of each isolation trip function shown
'2 in Table 3.3.2-3 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 months, where N is the total number of redundant channels in a specific isolation trip system.
*An inoperable channel need not be placed in the tripped condition where this
. would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours or the ACTION required by Table 3.3.2-1 'or that Trip Function shall be taken.
**The trip system need not be placed in the tripped condition if this would cause the Trip Function to occur. When a trip system can be placed in the a'
- tripped condition without causing the Trip Function to occur, place the trip
( .- system with the most inoperable channels in the tripped condition; if both systems have the same number of inoperable channels, place either trip system in the tripped condition. GRAND GULF-UNIT 1 3/4 3-9 Amendment No. 4 2 , .__
t4L M-ol P5o IN51RUWENTATION 2 TABLE 3.3.3-1 (Continued) lL EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION ACTION 30 -
' With the number of OPERABLE channels less than reoud -
i by the Minimum OPERABLE Channels per Trip Function requiret.. .:
- a. With one channel inoperable, place the i peracle channel in the tripped condition within one hour or ceclare the associated system (s) inoperable.
- b. With more than one channel inoperable, declare the associated sys.em(s) inoperable.
ACTION 31 - With the number of OPERABLE channels less than recuired by the Minimum OPERABLE Channels per -ip Function requirement, ceclare the associated ADS tr : system or ECCS inoperable. ACTION 32 f With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status witnin 6 hours
. or ceclare the associated ADS trip system or ECCS inoperacle.
ACTION 33 - With the numeer of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, p' ace the inoperable channel (s) in the tripped condition within one hour or declare the HPCS system inoperable. ACTIOh 34 - With the number of OPERABLE channelt less than reouired by the Minimum 0FERABLE Channels per Trip Nnction requirement, place - at least one itsoerable channel in the tripped condition within onehour\ordeclaretheHPCSsysteminoperable. ACTION 35 - With the number of OPERABLE channels less than ruouired by the Minimum OPERABLE Channels per Trip Function requirement, place the sinoperable channel (s) in the tripped condition within one l hour \ or declare the associated system (s) inoperable.
"!n; previsiens ;f f,pecificatica 2.0.4 era ac' cppliccble.
GRAND GULF-UNIT 1 3/4 3-30 p, andment , go;,20
, ,,g
-y N D ,J. k TABLE 3.3.6-1 a
j.
$ CONTROL ROD BLOCK INSTRUMENTATION E
=
5 o MINIMUM APPLICABLE E OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION PER TRIP FUNCTION CONDITIONS ACTION . Z 1. ROD PATTERN CONTROL SYSTEM r a. Low Power Setpoint 2 1, 2 60
- b. High Power Setpoint 2 1, 2 60
- 2. APRM
- a. Flow Biased Neutron Flux-4 Upscale 6. 1 61
- b. Inoperative 6 1, 2, 5 61 ,
- c. Downscale 6 1 61 i d. Neutron Flux - Upscale, Startup 6 2, 5 61 R
- 3. SOURCE RANGE MONITORS ,
61
- a. Detector not full in( 4 2 i T 2** 5 62 i *
- b. Upscale (b) 4 2 61 i
2** 5 62 1
- c. Inoperative (b) 4 2 61 2** 5 62
- d. Downscale(c) 4 2 61 2** 5 62 l
y k 4. INTERMEDIATE RANGE MONITORS f9 a. b. Detector not full in Upscale 6 6 2, 2, 5 5 61 61
- c. Inoperati 6 2, 5 61
- d. Downscale{g) 6 2, 5 61 7
- 5. SCRAM DISCHARGE VOLUME
- a. Water Level-High 2 1, 2, 5* 62 1 6. REACTOR COOLANT SYSTEM RECIRCULATION FLOW d
~
- a. Upscale 3 1 62 I 7. REACTOR MODE SWITCH SHUTDOWN POSITION 2 3, 4 63
fb2 lNL S$ 01 INSTRUMENTATION TABLE 3.3.6-1 (Continued) CONTROL R00 BLOCK INSTRUMENTATION ACTION ACTION 60 - Declare the RPCS inoperable and take the ACTION required by Specification 3.1.4.2. ACTION 61 - With the number of OPERABLE Channels:
- a. One less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 7 days or place the inoperable channel in the tripped condition witbin the next hour.
- b. Two or more less than required by the Minimum OPERABLE
, Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within t
one hour. ACTION 62 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within one hour. ACTION 63 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, initiate a rod block. NOTES ,
- With more than one control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
** OPERABLE channels must be associated with SRMs required OPERABLE per Specification 3.9.2.
(a) This function shall be automatically bypassed if detector count rate is
> 100 cps or the IRM channels are on range 3 or higher.
(b) This function shall be automatically bypassed when the associated IRM ) channels are on range 8 or higher. (c) This function shall be automat.Nally bypassed when the IRM channels are on range 3 or higher. (d) Triis function shall be automatically bypassed when the IPM channels are on range 1. . 1 (c) M e previsient c? Speci#ication 2.0.' are n0+ 2pplicable f 0r enter";; v,_._ . . , ~ . . . . . . . . i I GRAND GULF-UNIT 1 3/4 3-f tevoMwf N. - l L
- Ps3 NL. SS -of .
INSTRUMENTATION 3/4.3.7 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.1 The radiation monitoring instrumentation channels shown in Table 3.3.7.1-1 shall be OPERABLE with their alarm / trip setpoints within the specified limits. APPLICABILITY: As shown in Table 3.3.7.1-1. ACTION:
- a. With a radiation monitoring instrumentation channel alarm / trip setpoint exceeding the value shown in Table 3.3.7.1-1, adjust the setpoint to within the limit within 4 hours or declare the channel inoperable,
- b. With one or more radiation monitoring channels inoperable, take the ACTION required by Table 3.3.7.1-1.
- c. The provisions of Specificationf 3.0.3 =d 3.0.' are not applicable.
SURVEI'. LANCE REQUIREMENTS 4.3.7.1 Each of the above required radiation monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the conditions a,nd at the frequencies shown in Table 4.3.7.1-1. l GRAND GULF-UNIT 1 3/4 3-58 buesent Wo. _
rs4 NL SS-on ! l INSTRUMENTATION
' h.
SEISMIC MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.2 The seismic monitoring instrumentation shown in Table 3.3.7.2-1 shall be OPERABLE. APPLICABILITY: At all times. ACTION:
- a. With one or more of the above required seismic monitoring instrumen.>
inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next
, 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status.
- b. The provisions of Specificationk 3.0.3 rd LO.' are not applicable.
y SURVEILLANCE REQUIREMENTS 4.3.7.2.1 Each of the above required seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNC-TIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.2-1. . 4.3.7.2.2 Each of the above required seismic monitoring instruments actuated during a seismic event greater than or equal to10.01 g shall be restored to OPERABLE status within 24 honrs and a CHANNEL CALIBRATION performed within 5 days following the seismic event. Data shall be retrieved from acj.uated
. instruments and analyzed to determine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days describing the magnitude, frequency spectrum and resultant effect upon unit features important to L, safety.
i:"~) GRAND GULF-UNIT 1 3/4 3-63 AMNWA No.
FES NL SE -ol INSTRUMENTATION - $4 METEOROLOGICAL MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.3 The meteorological monitoring instrumentation channels shown in Table 3.3.7.3-1 shall be OPERABLE. APPLICABILITY: At all times. . ACTION:
- a. With one or more required meteorological monitoring instrumentation channels inoperable for more than 7 days, prepare and submit a '
Special Report to th.e Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and
/ the plans for restoring the instrumentation to OPERABli status.
- b. The provisions of Specification 3.0.3 ;nd 3.0.' are not applicable.
. . ; SURVEILLANCE REQUIREMENTS .
4.3.7.3 Each of the above required meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.3-1. g e e G G, RAND GULF UN T1 3/4 3-66 Amsuonrwr bL.
P"% ML Sk 01 INSTRUMENTATION
; TRAVERSING IN-CORF PROBE SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.7. The traversing in-core probe system shall be OPERABLE with:
- a. Five movable detectors, drives and readout equipment to map the core, and
- b. Indexing equipment to allow all five detectors to be calibrated in a common location.
APPLICABILITY: When the traversing in-core probe is used for:
- a. Recalibration of the LPRM detectors, and b.f Monitoring the APLHGR, LiiGR, MCPR, or MFLPD.
ACTION: With the traversing in-core probe system inoperable, do not use the system for theaboveapp)licablemonitoringorcalibrationfunctions.Theprovisionsof Specification 3.0.3 :nd 3. 0. ' are not applicable. SURVEILLANCE REQUIREMENTS 4.3.7.7 The traversing in-core probe system shall be demonstrated OPERABLE by normalizing each of the above required detector outputs within 72 hours prior to use when required for the LPRM calibration function.
"Only the detector (s) in the location (s) of interest are required to be OPERABLE.
GRAND GULF-UNIT 1 3/4 3-78 AmowMr Wo.
P57 NL 85-on _ INSTRUMENTATION FIRE DETECTION INSTRUMENTATION , LIMITING CONDITION FOR OPERATION 3.3.7.9 As a minimum, the fire detection instroentation for each fire detection zone shown in Table 3.3.7.9-1 shall be OPERABLE. APPLICABILITY: Whenever equipment protected by the fire detection instroent is required to be OPERABLE. , ACTION: With the number of OPERABLE Function A or Function B fire detection instruments less than the Minimum Instruments OPERABLE, requirement of Table 3.3.7.9-1:
- a. Within 1 hour, establish a fire watch patrol to inspect the zone (s) with the Function A or room (s) with Function B inoperable instre ment (s) at least once per hour, unless the instraent(s) is located inside the containment, steam tunnel or drywell, then inspect the primary containment at least once per 8 hours or monitor the contain-ment, steam tunnel and/or drywell air tengerature at least once per hour at the locations listed in Specification 3.7.8, 4.6.1.8 and 4.6.2.6. -
- b. Restore the minimum number of instruments to OPERABLE status within 14 days or prepare and submit a Special Report to the Comission pur-suant to Specification 6.9.2 within 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status.
- c. TheprovisionsofSpecificationk 3.0.3 4-4 3.0.1 are not applicable.
1 SURVEILLANCE REQUIRENENTS 4.3.7.9.1 Each of the above required fire detection instraents which are cccessible during unit operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST. Fire detectors which are not accessible during unit operation shall be demonstrated OPERABLE by the
. performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTOOWN exceeding 24 hours unless performed in the previous 6 months.
4.3.7.9.2 The NFPA Standard 720 supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months. GRAND GULF-UNIT 1 3/4 3-80 bevowns k -
- ..--.~---~~~-~-*~~~~'***'**'"'~~~~~'***"'
P5WR NL SS-ol INSTRUMENTATION [k LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FOR OPERATION + 3.3.7.10 The loose part detection system shall be OPERABLE. APPLICABILITY: OPERATION.\L CONDITIONS 1 and 2. ACTION:
- a. With one or more loose part detection system channels inoperable for more than 30 days, prepare and submit a Special Report to the Commis-sion pursuant to Specification 6.9.2 within the next 10 days outlining the~ cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status,
- b. 'The provisions of Specification 3.0.3 :nd 2.0.' are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.7.10 Each channel of the loose part detection system shall be demonstrated OPERABLE by performance of a:
- a. CHANNEL CHECK at least once per 24 hours,
- b. CHANNEL FUNCTIONAL TEST at least once per 31 days, and
- c. CHANNEL CALIBRATION at least once per 18 months.
/
GRAND GULF-UNIT 1 3/4 3-90 A mtw d** wf N*. ! I
64L BS-ot l l INSTRUMENTATION . RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.11 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (00CM). APPLICABILITY: At all times. ACTION: I a. With a radioactive liquid effluent monitoring instrumentation channel I alarm / trip setpoint less conservative than required by the above . specification, immediately suspend the release of radioactive liquid (' effluents monitored by the affected channel or declare the channel inoperable,
- b. With less than the minimum number of radicar.tive liquid effluent monitoring instrumentation channels OPERA 3LE, take the ACTION shown in Table 3.3.7.11-1. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION and, if f
unsuccessful,-explain why this inoperability was not corrected in a ( timely manner in the next Semiannual Radioactive Effluent Release Report.
- c. The provisions of Specification 3.0.3 =d 2.0.C are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.7.11 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.11-1. [ GRAND GULF-UNIT 1 3/4 3-91 ggg 4,
4 Pbc> NL 8% -o\ TABLE 3.3.8-1 (Continued) j,. [h.. PLANT SYSTEMS ACTUATION INSTRUMENTATION w tp ACTION ACTION 130 - a. With the number of OPERABLE channels one less than required , by the Minimum OPERABLE Channels per Trip System requirement, place the inoperable channel in the tripped condition within one hour; otherwise, declare the associated containment spray system inoperable and take the action required by Tech-nical Specification 3.6.3.2.
- b. With the number of OPERABLE channels two less than required by the Minimum OPERABLE channels per Trip System require-ment, declare the associated containment spray system inoperable and take the action required by Technical Specification 3.6.3.2.
ACTION 131 - With the number of OPERABLE channels less than requires by the Minimum OPERABLE Channels per Trip System requirement, restore the inoperable channels to OPERABLE status within one hour; other-
/ wise, declare the associated containment spray system inoperable i
ar,d take the action required by Technical Specification 3.6.3.2. ACTION 132 - For the feedwater system / main turbine trip system:
- a. With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels requirement, restore the inoperable channel to OPERABLE status within 7 days or be in at least STARTUP within the next 6 hours.
( b. With the number of OPERABLE channels two less than required by the Minimum OPERABLE Channels per Trip System require-ment, restore at least one of the inoperable channels to OPERABLE status within 72 hours or be in at least STARTUP within the next 6 hours. ACTION 133 - With the number of OPERABLE ch; .<ls less than required by the Minimum OPERABLE Channels per hip System requirement, declare the associated suppresson pool makeup system inoperable and take the action required by Specification 3.6.3.4. ACTION 134 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, restore the inoperable channels to OPERABLE status within 8 hours; other-wise, declare the associated suppression pool makeup system inoperable and take the action required by Specification 3.6.3.4. ACTION 135 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement:
- a. With one channel inoperable, place the ipoperable channel in the tripped condition within one hourg or declare the associated system (s) inoperable.
- b. With more than one channel inoperable, declare the associated system (s) inoperable.
'*The preM;i;r; ef Spccific;tiO^ 3.0.' r^ ^^t Opp!k2h.
GRAND GULF-UNIT 1 3/4 3-107 bawow d.. }
< s
.NL BS ol REACTOR COOLANT SYSTEM 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.4.7 Two main steam line isolation valves (MSIVs) per main steam line shall be OPERABLE with closing times greater than or equal to 3 and less than or equal to 5 seconds.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3. ACTION: a With one or more MSIVs inoperable:
- 1. Maintain at least one MSIV OPERABLE in each affected main steam line that is open and within 8 hours, either:
a) Restore the inoperable valve (s) to OPERABLE status, or b) Isolate the affected main steam line by use of a deactivated MSIV in the closed position.
- 2. Otherwise, be in at least HOT SHUT 00WN within the next 12 hours and in COLD SHUT 00WN within the following 24 hours.
S. The previciens of Speci'ic: tier 2.0.d are not :pp!! cab!:. SURVEILLANCE REQUIREMENTS 4.4.7 Each of the above required MSIVs shall be demonstrated OPERABLE by verifying full closure between 3 and 5 seconds
- when tested pursuant to Specification 4.0.5. The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITIONS 2 or 3 provided the surveillance is performed within 12 hours after reaching a reactor steam pressure of 600 psig and prior to entry into OPERATIONAL CONDITION 1.
*The 3 seconds is the time measured from start of valve motion to complete valve closure. The 5 seconds is the time measured from initiation of the actuating signal to complete valve closure.
GRAND GULF-UNIT 1 3/4 4-24 bewoum No. -
* ' Plo?.-
ut SS-ol . REACTOR COOLANT SYSTEM 3/4.4.3 STRUCTURAL INTEGRITY r LIMITIME C ITIONFUROPERATION i 3.4.8 The structural integrity of ASME Code Class 1,1 and 3 components shall be maintained in accordance with Specification 4.4.8. ' APPLICA81LITY: OPERATION L COMOITIONS 1, 2, 3, 4 and 5. ACTION:
- a. With the structural integrity of any ASME Code Class 1 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50*F above the minimum temperature required by NOT considerations,
- b. With the structural integrity of any ASME Code Class.2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its Itait or isolatp the affected component (s) prior to increasing the Reactor Coolant i System temperature above 200'F.
- c. With the structural integrity of any ASME Code Class 3 component (s) not confereing to the above requirements, restore the structural '
integrity of the affected component (s) to within its limit or isolatlt {, the affected component (s) from service,
- d. TM ;=!*4 ens-of Sprificatien 3.4.' = .at ;;HeeMe.
SURVEILLANCE REQUIREMENTS 4.4.8 No requirements other than Specification 4.0.5.
': l l
GRMD GULF-UNIT 1 3/4 4 25 beJone4 V*. k
6!L S E - 01 %3 4 REACTOR COOLANT SYSTEM
- i. .
9 [W COLD SHUT 00VN , LIMITING CONDITION FOR OPERATION 3.4.9.2 Two# shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and, unless at least one re:irculation pump is in operation, at least one shutdown cooling mode loop shall be in operation *'N with each loop consisting of at least:
- a. One OPERABLE RHR pump, and
- b. One OPERABLE RHR heat exchanger.
APPLICABILITY: OPERATIONAL CONDITION 4. ACTION:
- a. With less than the above required RHR shutdown cooling mode loops OPERABLE, within one hour and at least once per 24 hours thereafter, demonstrate the operability of at least one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling mode loop.
- b. With no RHR shutdown cooling mode loop in operation, within one hour establish reactor coolant circulation by an alternate method and monitor k.- reactor coolant temperature and pressure at least once per hour.
- c. h e peoutsicas of-Specificatica 3. . ' :rc net :pp1 4:b h.**
SURVEILLANCE REQUIREMENTS 4.4.9.2 At least one shutdown cooling mode loop of the residual heat removal system or alternate method shall be determined to be in operation and circulating reactor coolant at least once per 12 hours.
'One RHR shutdown cooling mode loop may be inoperable for up to 2 hours for surveillance testing provided the other loop is OPERABLE and in operation.
*The shutdown cooling pump may be removed from operation for up to 2 hours per 8 hour period provided the other loop is OPERABLE.
##The shutdown cooling mode loop may be removed from operation during hydrostatic testing.
( - **Thh caceptior-i' :pplicable unt!' ct+*Wp-f+ee-the-second refviling cuteser 3/4 4-27 Amendment No.f 3S - GRAC GULF-UNIT 1
ML iM-ol PG:4 EMERGENCY CORE COOLIN'G SYSTEMS 3/4 5.2 ECCS - SHUT 00W
, LIMITING CONDITION FOR OPERATION 3.5.2 At least two of the following shall be OPERABLE:
a. The low pressure core spray (LPCS) system with a flow path capable of taking suction from the suppression pool and transferring the water through the spray sparger to the reactor vessel.
- b. Low pressure coolant injection (LPCI) subsystem "A" of the RHR system with a flow path capable of taking suction from the suppression pool upon being manually realigned and transferring the water to the reactor vessel.
- c. Low pressure coolant injection (LPCI) subsystem "B" of the RHR systec, with a flow path capable of tiking suction from the suppression pool
- upon being manually realigned and transferring the water to the
. reactor vessel, d.
Low pressure coolant injection (LPCI) subsystem "C" of the RHR system with a flow path capable of takin'g suction from the suppression pool upon being manually realigned and transferring the water to the reactor vessel.
- e. The high pressure core spray (HPCS) system with a flow path capable of taking suction from one of the following water sources and trans-ferring the water through the spray sparger to the reactor vessel:
- 1. From the suppression pool, or k
- 2. When the suppression pool level is less than the limit or is
- : drained, from the condensate storage tank containing at least 170,000 available gallons of water, equivalent to a level of 18 feet.
APPLICABILITY: OPERATIONAL CONDITION 4 and 5*.
.c ACTION:
- a. With one of the above required subsystems / systems inoperable, restore at least two subsystems / systems to OPERABLE status within 4 hours or suspendalloperationsthathaveapotentialfordrainingthereagr vessel. -9: pr:d:fon: ef Spe:!'icatica 3.0.' :re net app!! cab!:1
- b. With both of the above required subsystems / systems inoperable, suspend CORE ALTERATIONS and all operations that have a potential for draining the reactor vessel. Restore at least one subsystem / system to OPERABLE status within 4 hours or establish SECONDARY CONTAINMENT INTEGRITY p ;r pwithin the next 8 houMen _- operatirig
-- _ under -this ACTION "The ECCS is not required to be OPERABLE provided that the reactor vessel head
'is removed, the cavity is flooded, the reactor cavity and transfer canal gates "in the upper containment pool are removed, and water level is maintained within '
the limits of Specifications 3.9.8 and 3.9.9. Tht: := w t4en i: applica5!e ent!' Ete"tt? S- the 5400^d "?'US'4^; OUt??? GRAND GULF-UNIT 1 3/4 5-6 Acendment No. 40,-
v; gg 5%5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 SUPPRESSION POOL LIMITING CONDITION FOR OPERATION
~.
3.5.3 The suppression pool shall be OPERABLE:
- a. In OPERATIONAL CONDITION 1, 2 or 3 with a contained water volume of at least 135,291 ft), equivalent to a level of 18'4-1/12."
b. In OPERATIONAL CONDITION 4 or 5" with a contained water volume of at least 93,600 ft), equivalent to e level of 12'8", except that the suppression pool level may be less than the limit or may be drained provided that:
- 1. No operations are performed that have a potential for draining tb reactor vessel, i '
- 2. The reactor mode switch is locked in the Shutdown or Refuel position,
- 3. The condensate storage tank contains at least 170,000 available gallons of water, equivalent to a level of 18', e.nd
- 4. The HPCS system is OPERABLE per Specification 3.5.2 with -an OPERABLE flow path capable of taking suction from the condensate storage tank e and transferring the water through the spray sparger to the reactor vessel.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4 and 5".
.,. ACTION:
- a. In OPERATIONAL C0NDITION 1, 2 or 3 with the suppression pool water level less than the above limit, restore the wate.- level to within the limit within I hour or be in at least HOT SHUTOOWN within the next 12 hours and in COLD SHUTOOWN within the following 24 hours,
- b. In OPERATIONAL CONDITION 4 or 5* with the suppression pool water level hss than the above limit or drained and the above required conditions not satisfied, suspend CORE ALTERATIONS and all opera-tions that have a potential for draining the reactor vessel and lock the reactor mode switch in the Shutdown position. Establish SECONDARY CONTA E NT_ INTEGRITY _wjthin 8_ hour _s.
~~ enoperatinP M.er'_thisXC.TIO.N,thecavitycan.notbe'd. rained.I-
,See Specification 3.6.3.1 for pressure suppression requirements.
l The suppression p.'ol it, not required to be OPERABLE provided that the reactor vestal head is removed, the cavity is flooded or being floodad from the suppression pool, tha reactor cavity and transfer cana's gates in tl . upper containment pool are removed when the cavity is flooded, and the water level is maintained within the limits of Specification 3.9.8 and 3.9.9. GRAND GULF-UNIT 1 3/4 5 8 Amendment No. 42,,_
1
~
AL ss on
; CONTAINMENT SYSTEMS Q
ORYWELL AIR LOCK , LIMITING CONDITION FOR OPERr: TION l 3.6.2.3 The drywell air lock shall be O'?El'A3LE with: .
- a. Both doors closed except when the air lock is being used for normal transit entry and exit through the drywell, then at least one air lock door shall be closed, and
- b. An overall air lock leakage rate of less than or equal to 2 scf per hour at P,,11.5 psig.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2* and 3.
, ACTION:
- a. With one d ywell air lock door inoperabl aintain at least the OPERABLE air lock door closed and either restore
-+:- [the inoperable air lock door to OPERABLE status within 24 hou lock the OPERABLE air lock door closed. Operation may then continue provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days. Otherwise, be in at least HOT
( SHUTDOW within the next 12 hours and in COLD SHUTDOWN within the following 24 hours. 4
), h0 7 70'.'i[ OII Of b70Ii* IIIi?" 3.0. Or0 I? I77) II 0.
- b. With the drywell air lock inoperable, except as a result of an inoperable i air lock door, maintain at least one air lock door closed; restore the
- inoperable air lock to OPERABLE status within 24 hours or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours,
- c. With one drywell air lock door inflatable seal system seal pressure instrumentation channel inoperable, restore the inoperable channel to 0PERABLE status within 7 days or verify the associated inflatable seal pressure to be 3, 60 psig at least once per 12 hot.'s.
^
"See Special Test Exce pion 3.10.1.
4 k GRAMD GULF-UNIT 1 3/4 6-15 Amendment No. 31, _
O e NL $8-01 M
. 3/4.7 PLANT SYSTEMS
~ _
3/4.7.1 SERVICE WATER SYSTEMS - bb STANDBY SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.1 Each of the following independent standby service water (SSW) system subsystems shall be OPERABLE with each subsystem comprised of:
- a. One OPERABLE SSW pump, and
- b. An OPERABLE flow path capable of taking suction from the associated SSW cooling tower basin and transferring the water through the RHR heat exchangers and to associated plant equipmeny., as required, shall be OPIRABLE as follows:
In OPERATIONAL CONDITIONS 1, 2, and 3: two subsystems; and 1. In OPERATIONAL CONDITIONS 4, 5, and *: the subsystems asso:iatec 2. with the systems and components required to be OPERABLE by Specifications 3.4. 5. 2, 3. 5. 2, 3. 8.1. 2, 3. 9.11.1 o r 3. 9.11. 2. APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4, 5 and *. ACTION:
- a. In OPERATIONAL CONDITION 1, 2 or 3:
- 1. With one SSW subsystem inoperable, restore the inoperable sub-
** system to OPERABLE status within 72 hours or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUT 00VN within the following 24 hours.
-{ 2. With both SSW subsystems inoperable, be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN ** within the following 24 hours,
- b. In OPERATIONAL CONDITION 3 or 4 with the SSW subaystem, which is asso-ciated with an RHR loop required OPERABLE by Specification 3.4.9.1 or 3.4.9.2, inoperable, declare the associated RHR loop inoperable and take the ACTION required by Specification 3.4.9.1 or 3.4.9.2, as appli-n:t :ppli::51: f:r cable. Th: pr:vi:!:n: Of Spect'ic"4
- ntry int: OPEPaTIOMLCOND:T!OM'd:n3.0.':r:
- c. In OPERATIONAL CONDITION 4 or 5 with the SSW subsystem, which is asso-ciated with an ECCS pump required OPERABLE by Specification 3.5.2, inoperable, declare the associated ECCS pump inoperable and take the ACTION required by Specificat n 3.5.2. -Th: pr:wi:i:n: Of !;::i'ics--
tier 3.0.' are ae+ epp'4cebia
=
When handling irradiated fuel in the primary or secondary containment.
- Whenever both S$W subsystems are inoperable, if unable to attain COLD SNUT00VN
- as required by this ACTION, maintain reactor coolant temperature,as low as practical by use of alternate heat removal methods.
#This exceptica is :pplic ble unti' :t:rtup frcr th: ::: nd refa: Ting 0;t:g^-
Amendment No. 35,- GRAND GULF-UNIT 1 3/4 7-1
P68 Nt. 9 Soot PLANT SYSTEMS LIMITING CONDITION FOR OPERATION ACTION: (Continued)
- d. In OPERATIONAL CONDITION 5 with the SSW subsystem, which is associated with an RHR system required OPERABLE by Specification 3.9.11.1 or 3.9.11.2, inoperable, declare the associated RHR system inoperable and take the ACTION required by Specification 3.9.11.1 or 3.9.11.2, asapplicabje.-Thepr:vi:f:r.:
-- s u.w3.
of Spect'ic: tier ?.0.' : : et
- e. kn OhRATh0NAL CONDITION *, with the SSV subsystem, which is asso:iate:
with a diesel generator required OPERABLE by Specification 3.8.1.2, inoperable, declare the associated diesel generator inoperable and take the ACTION required by Specification 3.8.1.2. The provisions of Specification 3.0.3 are not applicable,
- f. In OPERATIONAL CONDITIONS 1, 2, 3, 4, or 5 with the SSV subsystem, which is associated with a diesel generator required OPERABLE by Specification 3.8.1.1 or 3.8.1.2, inoperable, declare the associated diesel generator inoperable and take the ACTION required by Specification 3.8.1.1 or 3.w l.2 as applicable.
SURVEILLANCE REQUIREMENTS _ 4.7.1.1 At least the above required standby service water system subsystem (s) shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying that each valve in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position,
- b. At least once per 18 months during shutdown by verifying that each automatic valve servicing safety related equipment actuates to its correct position on an actuation test signal, i
1
'Tri: eu i: :pplic:b1: urt startup 're- tu ser:M refu '^; euts;e ]
GRAND GULF-UNIT I 3/4 7-2 A.tendment No. 78. 31,
%c\
. NL- 19 -Cl PLANT SYSTEMS 3/4.7.5 SEALED SOURCE CONTf.MINATION (h: 4
- l LIMITING ~ CONDITION FOR OPERATION 3.7.5 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 10 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcuries of removable contamination.
APPLICABILITY: At all times. ACTION:
- a. With a sealed source having removable contamination in excess of the above limit, withdraw the sealed source from use and either:
- 1. Decontaminate and repair the sealed source, or
- 2. Dispose of the sealed source in accordance with Commission Regulations,
- b. The provisions of Specification \ 3.0.3 =d 2.0.' are not applicable.
[ , SURVEILLANCE REQUIREMENTS 4.7.5.1 Test Requirements - Each sealed suurce shall be tested for leakage and/or contamination by:
- a. The licensee, or
- b. Other persons specifically authorized by the Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample. 4.7.5.2 Test Frequencies - Each category of sealed sources, excluding startup scarces and fission detectors previously subjected to core flux, shall be tested at the frequency described below.
- a. Sources in use - At least once per six months for all sealed sources containing radioactive material:
- 1. With a half-life greater than 30 days, excluding Hydrogen 3, and
- 2. In any form other than gas.
GRAND GULF-UNIT 1 3/4 7-15 herv0Wat k. -
eto hl S% -et r PLANT SYSTEMS
. 3/4.7.6 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.6.1 The fire suppression water system shall be OPERABLE with:
- a. At least two OPERABLE fire suppression fire pumps, each with a capacity of 1500 gpm, with their discharge aligned to the fire suppression header,
- b. Separate fire water storage tanks, each with a minimum contained volume of 210,000 gallons, and
- c. An OPERABLE flow path ccpable of taking suction from the "A" fire water storage tank and the "B" fire water storage tank and transferring the water through distribution piping with OPERABLE sectionalizing
,. control or isolation valves to the yard hydrant curb valves, the last valve ahead of the water flow alarm device on each sprinkler or hose standpipe and the last valve ahead of the deluge valve on each deluge or spray system required to be OPERABLE per Specifications 3.7.6.2, 3.7.6.5, and 3.7.6.6.
APPLICABILITY: At all times. ACTION:
- a. With one of the above required fire pumps and/or one fire water storage tank inoperable, restore the inoperable equipment to OPERADLE status within 7 days or provide an alternate backup pump or supply. The provisions of Specification \ 3.0.3 c...d 0.^.i are not applicable.
- b. With the fire suppression water system otherwise inoperable, establish a backup fire suppression water system within 24 hours.
SURVEILLANCE REQUIREMENTS 4.7.6.1.1 The fire suppression water system shall be demonstrated OPERABLE:
- a. At least once per 7 days by verifying the minimum contained water supply volume.
- b. At least once per 31 days by starting the electric motor driven fire suppression pump and operating it for at least 15 minutes,
- c. At least once per 31 days by verifying that each valve, manual, power operated or automatic, in the flow path is in its corrcet position.
- d. At least once per 12 months by cycling each testable valve in the (J
flow path through at least one complete cycle of full travel. GRAND GULF-UNIT 1 3/4 7-17 biuWJT b.
Pit WL W OI . . PLAhi SYSTEMS SPRAY AND/OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.6.2 The following spray / sprinkler systems shall be OPERABLE:
- a. Diesel Generator Building
- 1. Diesel Generator A pre-action sprinkler system N1P64D142A
- 2. Diesel Generator B pre-action sprinkler system N1P64D142B
- 3. Diesel Generator C pre-action sprinkler system N1P640142C
- b. Auxiliary Building *
- 1. Elevation 93'/103' Northeast Corridor N1P64D150
- 2. Elevation 119' Northeast Corridor N1P64D151
' 3. Elevation 139' Northeast Corridor N1P64D152
- 4. Elevation 166' Northeast Corridor HIP 64D153
- 5. Elevation 119' West Corridor N19640158
- 6. Elevation 139' West Corridor HIP 64D159
- 7. Elevation 166' Northwest Corridor N1P64D162
- c. Control Building * ,-
- 1. Elevation 148' Lower Cable Room N1P64D154 P. Elevation 189' Upper Cable Room N1P64D155
- 4. Elevation 93' NSP64D140
- d. Fire Pump House
- NSP64D136A/B APPLICABILITY: Whenever equipment protected by the spray / sprinkler systems is required to be OPERABLE.
ACTION:
- a. With one or more of the above required spray and/or sprinkler systems inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant .
systems or components could be damaged; for other areas, establish an hourly fire watch h trol.
- b. The provisions of Specification 3.0.3 r d 3.D.' are not applicable.
SURVEILLANCE REQUIRE)Th'S 4.7.6.2 The above required spray and sprinkler systems shall be demonstrated OPER2LE: .,
- a. At least once per 31 days by verifying that each valve, manual, power operated or automatic, in the flow path is in its correct position.
"Wet pipe sprinkler system.
GRAND QULF-UNIT 1 3/4 7-20 Amendment No. 15,-
P72. f4L SS-61 PLANT SYSTEMS 8 CO SYSTEMS 2 LIMITING CONDITION FOR OPERATION 3.7.6.3 The following low pressure CO2 systems shall be OPERA 8LE: Area location System Number Electrical Penetration Room Auxiliary Bldg. El. 139'0" N1P640201A, B, C, D Auxiliary Bldg. El. 119'0" N1P640200A, 8, C, D Electrical Penetration Room . Control Cabinet Room Control Bldg. El. 189'0" N1P640216 Division I Switchgear Room Control Bldg. El. 111'0" N1P640207 Division III Switchgear Room Control Bldg. El 111'0" N1P640209 Division II Switchgear Room Control Bldg. El. 111'0" N1PS40208 Emergency Shutdown Panel Rm Control Bldg. El. 111'0" N1P640212 Motor Generator Room Control Bldg. El. 148'0" N1P6402148 Electrical Switchgear Room Auxiliary Bldg. El. 166'0" N19640217A, B Lower Cable Spreading Room Control Bldg. El. 148'0" N1P640213 Upper Cable Spreading Room Control Bldg. El. 189'0" N1P640215 APPLICABILITY: Whenever equipment protected by the CO2 systems is required to be OPERABLE. ACTION:
- a. With one or more of the above required CO, systems inoperable, within one hour establish a continuous fire watch with backup fire suppres-sion equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol,
- b. The provisions of Specification 3.0.3.;nd 2.0.i are not applicable.
GRAND GULF-UNIT 1 3/4 7-22 bswoMe4 4.
P75 NL SS at PLANT SYSTEMS HALON SYSTEMS .
}
LIMITING CONDITION FOR OPERATION 3.7.6.4 The following Halon systems shall be OPERABLE with the storage tanks having at least 95% of full charge weight and 90% of full charge pressure:
- a. Control Building, elev.148'0 , Computer and Control Panel Room
- b. Control Building, elev.166'0", PGCC Under Floor Area
- c. Control Cabinet Room, elev.189'0", PGCC Under floor Area APPLICABILITY: Whenever equipment protected by the Halon systems is required .
to be OPERABLE. ACTION:
- a. With one or more of the above required Halon systems inoperable, within
! one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol,
- b. The provisions of Specificationk 3.0.3 cd ? A' are not applicable.
SURVEILLANCE REQUIREMENTS 1 4.7.6.4 Each of the above required Halon systems shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying that each valve, manual, power operated or automatic. except for hazard area selector valves l
F497G and F497H, in the flow path is in its correct position,
- b. At least on:e per 5 months by verifying Halon storage tank weight and pressure.
- c. At least once per 18 months by:
- 1. Verifying that the system, including associated ventilation system fire damper logic, actuates automatically upon receipt of a simulated actuation signal (Actual Halon release, Halon bottle initiator valve actuation, and electro-thermal link burning may be excluded from the test), and
- 2. Performance of a flow test through headers and nozzles to assure no blockage, and
- 3. Exercising each ventilation system fire damper to the closed position and verifying the dampers move freely.
GRAND GULF-UNIT 1 3/4 7-24 Ltwowur u _
-. s P74 INL 65-01
' PLANT SYSTEMS
~
;e.O FIRE HOSE STATION _S .
LIMITING CONDITION FOR OPERATION 3.7.6.5 The fire hose stations shown in Table 3.7.6.5-1 shall be OPERABLE. APPLICABILITY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE. ACTION:
- a. With one or more of the fire hose stations shown in Table 3.7.6.5-1 inoperable, route an additional fire hose of equal or greater diameter to the unprotected area (s) from an OPERARLE hose station within 1 hour if the inoperable fire hose is the primary means of fire suppression; otherwise, route the additional hose within 24 hours.
- b. TheprovisionsofSpecification\3.0.3rd?_A A
are not applicable. SURVEILLANCE REQUIREMENTS 4.7.6.5 Each of the fire hose stations shown in Table 3.7.6.5-1 shall be demonstrated OPERABLE:
- a. At least once per 31 days by a visual inspection of the fire hose stations accescible during plant operation to assure all required equipment is at the station,
- b. At least once per 18 months by:
- 1. Visual inspection of the fire hose stations not accessible during plant operation to assure all. required equipment is at the station.
- 2. Removing the hose for inspection and re-racking, and
- 3. Inspecting all gaskets and replacing any degraded gaskets in the couplings.
- c. At least once per 3 years by:
- 1. Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage.
- 2. Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above the maximum fire main operating pressure, whichever is greater, j .w, GRAND Gui,F-UNIT 1 3/4 7-25 b oa45.et No. -
Pf5 HL %1-01 PLANT SYSTEMS YARD FIRE HYORANTS AND HYDRANT HOSE HOUSES LIMITING CONDITION FOR OPERATION 3.7.6.6 The yard fire hydrants and associated hydrant hose houses shown in Table 3.7.6.6-1 shall be OPERABLE. APPLICABILITY: Whenever equipment in the areas protected by the yard fire hydrants is required to be OPERABLE. I ACTION:
- a. With one or more of the yard fire hydrants or associated hydrant hose houses shown in Table 3.7.6.6-1 inoperable, route sufficient additional lengths of fire hose of equal or greater diameter located in an adjacent
.- OPERABLE hydrant hose house to provide service to the unprotected area (s) within 24 hours.
- b. The provisions of Specificationk 3.0.3 nd 2.0.' are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.6.6 Each of the yard fire hydrants and associated hydrant hose houses shown in Table 3.7.6.6-1 shall be demonstrated OPERABLE: l l a. At least once per 31 days by visual inspection of the hydrant hose house to assure all required equipment is at the hose house.
- b. At least once per 6 months, during March, April or May and during September, October or November, by visually inspecting each yard fire hydrant and verifying that the hydrant barrel is dry and that the l tydrant is not damaged.
- c. At least once per 12 months by:
- 1. Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above the maximum fire main operating pressure whichever is greater.
- 2. Replacement of all degraded gaskets in couplings.
- 3. Performing a flow check of each hydrant.
GRAND GULF-UNIT 1 3/4 7-28 6agwr 6, s
pg NL SS-ot l PLANT SYSTEMS 3/4.7.7 FIRE RATED ASSEMBLIES LIMITING CONDITION FOR OPERATION 3.7.7 All fire rated assemblies (walls, floor / ceilings, cable tray enclosures and other fire barriers) separating safety related fire areas or separating portions of redundant systems important to safe shutdown within a fire area, and all sealing devices in fire rated assembly penetrations (fire doors, fire windows, fire dampers, cable and piping penetration seals and ventilation seals) shall be OPERABLE.
. APPLICABILITY: At all times.
ACTION:
- a. With one or more of the above required fire rated assemblies and/or sealing devices inoperable, within one hour establish a continuous i fire watch on at least one side of the affected assembly (s) and/or sealing device (s) or verify the OPERABILITY of fire detectors on at least one side of the inoperable assembly (s) and/or sealing device (s) and establish an hourly fire watch patrol,
- b. The provisions of Specificationk 3.0.3 cd 2.0.* are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.7.1 Each of the above required fire rated assemblies and sealing devices , shall be verified OPERABLE at least once per 18 months by performing a visual inspection of:
- a. The exposed surfaces of each fire rated assembly.
- b. Each fire window / fire damper and associated hardware, i
! c. At least 10 percent of each type of sealed penetration. If apparent changes in appearance or abnormal degradations are found, a visual inspection of an additional 10 percent of each type of sealed l penetration shall be made. This inspection process shall continue until a 10 percent sample with no apparent changes in appearance or abnormal degradation is found. Samples shall be selected so that each penetration seal will be inspected at least once per 15 years. i 1 GRAND GULF-UNIT 1 3/4 7-30 hussongwr No._ t
P77 , NL Il C:t i ELECTRICAL POWER SYSTEMS r: 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.4.1 All primary containment penetration conductor overcurrent protective devices shown in Table 3.8.4.1-1 shall be OPERABLE. APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3. ACTION:
-a, With one or more of the primary containment penetration conductor overcurrent protective devices shown in Table 3.8.4.1-1 inoperabic, declare the affected system or component inoperable and apply the appropriate ACTION statement for the affected system, and:
- 1. For 6.9 kV circuit breakers, de-energize the 6.9 kV circuit (s) by tripping the associated redundant circuit breaker (s) within 72 hours
, and verify the redundant circuit breaker to be tripped at least once per 7 days thereafter.
- 2. For 480 volt circuit breakers, remove the inoperable circuit breaker (s) from service by racking out the breaker within 72 hours and verify the inoperable breaker (s) to be racked out at least once per 7 days thereafter.
, Otherwise, be in at least HOT SHUTOOWN within the next 12 hours and in i
COLD SHUTDOWN within the following 24 hours,
- b. h^ pecuisi^^? cf Sp^c"icatica 3 ^ ^ ?"a aa+ =pp14r=h1= +a avae "*-^a+
device: ia S.9 cu etreutte owteg geye thej. redundant circuit bre:Eer: t-ipp^d e" to ADA ue1+ ciec"its 'hich heue tha iaoperebia ci-c"it b*^ 9^" r:ck:: Out. SURVEILLANCE REQUIREMENTS 4.8.4.1 Each of the primary containment penetration conductor overcurrent protective devices shown in Table 3.8.4.1-1 shall be demonstrated OPERABLE:
- a. At least once per 18 months:
- 1. By verifying that the medium voltage 6.9 kV circuit breakers are OPERABLE by selecting, on a rotating basis, at least 10% of the circuit breakers and performing:
a) A CHANNEL CALIBRATION of the associated protective relays, and b) An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and overcurrent control circuits function as designed and as specified in Table 3.8.4.1-1. (; GRAND GULF-UNIT 1 3/4 8-19 AmicomeA M._
I P73 dL SS-sl ! i i l REFUELING OPERATIONS i 3/4.9.11 RESIOUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11.1 At least one shutdown cooling mode train of the residual heat removal (RHR) systes shall be OPERABLE and in operation
- with at least:
- a. One OPERABLE RHR pump, and
- b. One OPERABLE RHR heat exchanger train.
APPLICABILITY: OPERATIONAL CONDITION 5, when irradiated fuel is in the rea: tor vessel and the water level is greater than or equal to 22 feet 8 inches above the top of the reactor pressure vessel flange. ACTION:
- a. With no RHR shutdown cooling mode train OPERABLE, within one hour and at least once per 24 hours thereaftsr, demonstrate the OPERABILITY of at least one alternate method capable of decay heat removal. Otherwise, suspend all operations involving an increase in the reactor decay heat load and
** establish SECONDARY CONTAINMENT INTEGRITY within 4 hours,
- b. With no RHR shutdown cooling mode train in operation, within one hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature at least once per hour, t % prevhhn; Of 0;;c;ificetien 3.0.4 . . imi. syylivsbir.# l SURVEILLANCE REQUIREMENTS 4.9.11.1 At least one shutdown cooling mode train of the residual heat removal system or alternate method shall be verified to be in operation and circulating reactor coolant at least once per 12 hours.
s "The shutdown cooling pump may be removed from operation for up to 2 hours per 8-hour period. Ah ::::pthr b :pplic:th =ti' ;tartup f r;; the se;;ad refveling ::t:g: 3/4 9-18 Amendsent No. 35,- l GRAND GULF-UNIT 1
- P19 F4L M -01 REFUELING OPERATIONS'
- {; . ' LOW WATER LEVEL , LIMITING CONDITION FOR OPERATION , 3.9.11.2 Two shutdown cooling mode trains of the residual heat removal (RHR) system shall be OPERALLE and at least one train shall be in operation,* with each train consisting of at least:
- a. One OPERABLE RHR pump, and
- b. One OPERABLE RHR heat exchanger train.
APPLICABILITY:
-OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor vessel ano the water level is less than 22 feet 8 inches above the top of the reactor pressure vessel flange.
ACTION: I
- a. With less than the above required shutdown cooling mode trains of the RHR system OPERABLE, within one hour and at least once per 24 hours thereafter, demonstrate the OPERABILITY of at least one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling mode train.
mode train in operation, within one hour *
- b. With no RHR shutdown coolin establish reactor coolant c rculation by an alternate method and monitor reactor coolant temperature at least once per hour. ~
=c. '5: prevhhn: Of Sp::ifi;;;ien 2.^.4 ere act ;ppli;;t h.# -
SURVEILLANCE REQUIREMENTS 4.9.11.2 At least one shutdown cooling mode train of the residual heat removal system or alternate method shall be verified to be in operation and circulating reactor coolant at least once per 12 hours. The shutdown cooling pump may be removed from operation for up to 2 hours per 8-hour period. k - This
# e c h u :ppite ele uato ste-tup ' - the te: nd ref;:Un; eut49+,-
Amendment No. 3E g 3/4 9-19 GRAC GULF-UNIT 1
1- '* ! 4-o L RADI0 ACTIVE EFFLUENTS P f'.. *
- f, Qg;, DOSE -
LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in-liquid effluents released, from each reactor unit' to UNRESTRICTED , AREAS (see Figure 5.1.3-1) shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 arem to the total body and to less than or equal to 5 mrem to any organ, and
- b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 arem to any organ.
APPLICABILITY: At all times. ACTION:
- a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Report which identifies the cause(s) for ext:eeding the limit (s) and defines the corrective actions that have
(, been taken to reduce the releases and the corrective actions to be taken to ensure that future releases will be in compliance with the l above limits. This Special Report shall also include (1) the results , of radiological analyses of the drinking water source and (2) the l radiological impact on finished drinkin to the requirements of 40 CFR Part 141 g water supplies with regard-
- b. TheprovisionsofSpecificationk3.0.3end-4 eor +arenotapplicable. g SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculations. Cumulative dose contributions from liquid effluu ts for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters of the 00CM at least once per 31 days.
- Applicable only if drinking water supply is taken from the receiving water
.t ' body within 3 miles downstream of the plant discharge.
\.
h GRAND GULF-UNIT 1 3/4 11-5 k w&AmK b -
7.-
! c *. gg t WL M OL e
e RADIOACTIVE EFFLUENTS h LIQUIO WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses 1 due to the liquid effluent from each reactor unit to UNRESTRICTED AREAS (see Figure 5.1.3-1) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ, in a 31-day period. APPLICABILITY: At all times. ACTION:
- a. With radioactive liquid waste being discharged without treatment f and in excess of the above limits, prepare and submit to the Commis-sion, within 30 days pursuant to Specification 6.9.2, a Special Report which includes the following information:
- 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, which resulted in liquid radwaste being discharged without treatment, and the reason for the inoperability, and
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action (s) taken to prevent a recurrence.
- b. TheprovisionsofSpecificationk3.0.3ud2.0.iarenotapplicable.
SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each reactor unit to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with method-ology and parameters in the 00CM. 4.11.1.3.2 The lastalled liquid radwaste system shall be demonstrated OPERABLE by meeting Specifications 3.11.1.1 and 3.11.1.2. l
~
GPAND GULF-UNIT 1 3/4 11-6 Q,w 4,
Ps1 l i NL SS-on RADIOACTIVE EFFLUENTS [h LIQUID HOLOUP TANKS
- l LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in any outside tempo-rary tank, not including liners for shipping radwaste, shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.
APPLICABILITY: At all times.
- ACTION:
- a. With the quantity of radioactive material in any of the above specified tanks exceeding the above limit, immediately suspend all
, additions of radioactive material to the tanks and within 48 hours reduce the tank contents to within the limit, and describe the events leading to the co:idition in the next Semiannual Radioactive Effluent Release Report,
- b. The provisions of Specification 3.0.3 ud 2.^.' are not applicable.
( SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above specified tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank,
- s. .-
(. GRAND GULF-UNIT 1 3/4 11-7 kwewt n u., -
?C5 NL64*01 RADI0 ACTIVE EFFLUENTS h DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site to ares, at and beyond the SITE BOUNDARY (see Figure 5.1.3-1) shall be limited-to the following:
- a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and
. b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
APPLICABILIH: At all times. I ACTION:
- a. With the calculated air dose from the radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to ensure that future releases will be in compliance with
' Specification 3.11.2.2.
- b. The provisions of Specification \ 3.0.3 rd 2 ^.' are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2 Dose Calculations. Cumulative dose contributions for noble gases for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the 00CM at least once per 31 days. C. GRAND GULF-UNIT 1 3/4 11-12 boggut 4. _
Ps4 NL M-61 RADIOACTIVE EFFLUENTS DOSE - 100!NE-131 IODINE-133. TRITIUM AND RADIONUCLIOES IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1.3-1) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 arem to any orgar., and
- b. During any calendar year: Less than or equal to 15 mrem to any organ.
APPLICABILITY: At all times. ACTION:
- a. With the calculated dose from the release of iodine-131, iodine-133, tritium and radionuclides in particulate form, with half-lives
( greater than 8 days, in gaseous effluents exceeding any of the above i limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce releases and the proposed corrective actions to be taken to ensure that future releases will be in compliance with Specification 3.11.2.3.
- b. TheprovisionsofSpecification\ 3.0.3-2-4 : 0.i are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations. Cumulative dose contributions from iodfre-131, iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the 00CM at least once per 31 days. GRAND GULF-UNIT 1 3/4 11' a e r K. , -
P85 NL S1-01 RADI0 ACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RA0 WASTE TREATMENT (OFFGAS) SYSTEM shall be in operation. APPLICABILITY: Whenever the main condenser air ejector system is in operation. ACTION:
- a. With gaseous radwaste from the main condenser air ejector system being discharged without treatment for more than 7 consecutive days, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:
- 1. Explanation of why gaseous radwaste was being discharged
, without treatment, identification of the inoperable equipment
! or subsystems which resulted in gaseous radwaste being discharged without treatment, and the reason for inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action (s) taken to prevent a recurrence,
- b. The provisions of Specification} 3.0.3c.4 0.0.i are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.4 The instruments specified in the 00CM shall be checked every 12 hours whenever the main condenser air ejector system is in operation to ensure that the GASEOUS RA0 WASTE TREATMENT (OFFGAS) SYSTEM is functioning. l l GRAND GULF-UNIT 1 3/4 11-14 bMM Wo. t
o * - P5(a NL 99 01 RADI0 ACTIVE EFFLUENTS
, lN VENTILATIONEXHAUSTTREATHENJ LIMITING CONDITION FOR OPERATION 3.11.2.5 The VENTILATION EXHAUST TREATHENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge whe.n the projected dose due to gaseous effluent releases from each reactor unit to areas at and beyond the SITE BOUNDARY (see Figure 5.1.3-1) in a 31 day period would exceed 0.3 mrem to any organ.
APPLICABILITY: At all times other than when the VENTILATION EXHAUST TREATMENT SYSTEM is undergoing routine maintenance." ACTION:
- a. With gaseous waste being discharged without treatment and in excess t of the above limits, prepare and submit to the Commission within 5
30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:
- 1. Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems which resulted in gaseous radwaste being
( discharged without treatment, and the reason for the inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action (s) taken to prevent a recurrence,
- b. The provisions of Specificationk 3.0.3 =d L1' are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from each reactor unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM. 4.11.2.5.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM shall be ! demonstrated OPERABLE by meeting Specifications 3.11.2.1 and 3.11.2.2 or
- 3.11.2.3.
[ I.. " Not applicable to Turbine Building ventilation exhaust unless filtration A' media is installed. GRAND GULF-UNIT 1 3/4 11 15 M W. -
r-ft'l NL ca oi .. RADIOACTIVE EFFLUENTS .' EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be limited to less than or equal to 4% by volume. APPLICABILITY: Whenever the main condenser offgas treatment system is in , operation. ACTION:
- a. With the concentration of hydrogen in the main condenser offgas treatment system exceeding the limit, restore the concentration to within the limit within 48 hours,
- b. The provisions of Specification { 3.0.3 rd 3.^ ' are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be determined to be within the above limits by monitoring the waste gas in the main condenser off gas treatment system with the hydrogen monitor OPERABLE as required by Table 3.3.7.12-1 of Specification 3.3.7.12. GRAND GULF-UNIT 1 3/4 11-16 broomtR.-
pgg WL $8 01 RADIOACTIVE EFFLUENTS 1
, 3/4.11.3 SOLID RADIOACTIVE 'ASTE W LIMITING CONDITION FOR OPERATION 3.11.3 The solid radwaste system shall be used in accordance with a PROCESS CONTROL PROGRAM to process wet radioactive wastes to meet shipping and burial ground requirements.
APPLICABILITY: At all times. ACTION:
- a. With the provisions of the PROCESS CONTROL PROGRAM not satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the site.
b.I TheprovisionsofSpecification\3.0.3d2.0.d are not applicable. SURVEILLANCE REQUIREMENTS 4.11.3 The PROCESS CONTROL PROGRAM shall be used to verify the. SOLIDIFICATION
- of at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste.
- a. If any test speciment fails to verify SOLIDIFICATION", the SOLIDI-FICATION" of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFI-CATION
- parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION.*
SOLIDIFICATION
- of the batch may then be resumed using the alternative SOLIDIFICATION
- parameters determined by the PROCESS CONTROL PROGRAM.
- b. If the initial test specimen from a batch of the waste fails to verify SOLIDIFICATION,* the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least 3 consecutive initial test specimens demonstrate SOLIDIFICATION.*
The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION
- of subsequent batches of waste.
*Except dewaterlag.
GRAND GULF-UNIT 1 3/4 11-18 M S.
NL SS"01 RADIOACTIVE EFFLUENTS
.f (2 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.
APPLICABILITY: At all times. ACTION: ,
- a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifi-cations 3.11.1.2.a 3.11.1.2.b, 3.11.2.2.a. 3.11.2.2.b, 3.11.2.3.a. or 3.11.2.3.b, calculations should be made including direct radiation I contributions from the reactor units and from outside storage tanks to determine whether the above limits of Specification 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commis-sion within 30 days, pursuant to Specification S.9.2, a Special Report
' that defines the corrective action to be taken to reduce subsequent
,. releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits.
( This Special Report, as defined in 10 CFR Part 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER 0F THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes
, the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition result-ing in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance it granted until staff action on the request is complete,
- b. TheprovisionsofSpecific& tion \3.0.3=d3.1*arenotapplicable.
SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the 00CM. 4.11.4.2 Cumulative dose contributions from direct radiation from the reactor I uni tt, and from radwaste storage tanks shall be determined in accordance with (0 the methodology and parameters in the 00CM. This requirement is applicable only under conditions set forth in Specification 3.11.4.a. GRAND GULF-UNIT 1 3/4 11-19 Auswo**1 d. I
$., iit - 0 L F10 3/4.12 RADIOLOGICAL ENVIRONMENTAL 190NITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION C.
, 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12.1-1.
APPLICABILITY: At all times. 7 ACTION:
- a. With the radiological environmental monitoring program not being s
conducted as specified in Table 3.12.1-1, prepare and submit to the Comission, in the Annual Radiological Environmental Operating Report per Specification 6.9.1.7, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
- b. With the level of radioactivity as the result of plant effluent in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12.1-2 when averaged over any calendar quarter, prepare and submit to the Comission within 30 days pursuant to Specification 6.9.2 a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be t
taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. When more than one of the radionuclides in Table 3.12.1-2 are detected in the sampling medium, this report shall be submitted if: concentration (1) reporting level (1) , concentration (2) reporting level (2) + * *'> 1.0 When radionuclides other than those in Table 3.12.1-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEM3ER OF THE PUBLIC is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Aeport.
- c. If milk or broad leaf vegetation sampling is relocated from one or more of the sample locations required by Table 3.12.1-1, identify new locations for obtaining repiscement samples and add them to the radiological environmental monitoring program within 30 days. In addition, report the cause(s) of the unavailability of samples and the new locations for obtaining replacement samples in the next Semi-annual Radioactive Effluent Release Report. Include in this report l the revised ODCM figure (s) and table (s) reflecting the new locations.
The specific locations from which samples were unavailable say then be deleted from the radiological environmental sonitoring program and the table (s) in the 00CM, provided the locations from which the replace-ment samples were obtained are added to the table (s) as replacement locations,
- d. The provisions of Specification \ 3.0.3-ee 3.0.' are not applicable.
k GRAND GULF-UNIT 1 3/4 12-1 Amendaent No. 21, I l l l
Mt. ff =ct _ RADIOLOGICAL ENVIRONMENTAL MONITORING y h7 3/4.12.2 LAND USE CENSUS j LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden of greater than 50 m 2 (500 ft 2) producing broad leaf vegetation. Broad leaf vegetation sampling of at least three different kinds of vegetation say be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted 0/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Tabla 3.12.1-1 shall be followed, including analysis of control samples. APPLICABILITY: At all times. ACTION:
- a. With a land use census identifying a location (s) which yields a
! calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.9.
- b. With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway)
( 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location (s) to the radiological environmental monitoring program within 30 days. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Identify the new location (s) in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table (s) for the ODCM
, reflecting the new location (s). ~
- c. The provisions of Specificationk 3.0.3 ud 0.0.i are not applicable.
SURVEILLANCE REQUIREMENTS , 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7. GRAND GULF-UNIT 1 3/4 12-11 bow 4,
Q gg .ot RADIOLOGICAL ENVIRONMENTAL MONITORING f 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION < 3.12.3 Analyses shall be performed on radioactive materials that correspond to samples required by Table 3.12.1-1. These materials are supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission. APPLICABILITY: At all times. ACITON:
- a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant
( to Specification 6.9.1.7.
- b. The provisions of Specification) 3.0.3 e .d 2.0.0 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.3 A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7. f r i b p GRAND GULF-UNIT 1 3/4 12-12 boy g, _ t
, NL St on N5 3 , hh. T h/4.0 APPLICABILITY ,
1 BAS , j The ecifications of this sectinn provide the general requirements applicable to eacl1 of the limiting Cc.1ditions for Operation and Surveil nce Requirements within Section 3/4. 3.0.1 Thi specification states the applicability of each sp ification in terms of defin d OPERATIONAL CONDITION or other specified app 1'cability conditioil and is p vided to delineate specifically when each s cification is ' applicable. 3.0.2 This specif ation defines those conditions ne essary to constitute compliance with the terms of an individual Limiting Cond' ion for Operation and associated ACTION reau ement. 3.0.3 This specificatioi. delineates the measu s to be taken for those circumstances not directly prov ed for in the ACT, N statements and whose occurrence would violate the int tofthespecification. For example, Specification 3.7.2 requires two c ntrni room ergency filtration subsystams to be OPERABLE and provides explici ACTION r uirements if one subsystem is C, inoperable. Under the requirements o Speci ication 3.0.3, if both of the required subsystems are inoperable, wi in ne hour measures roust be initiated to place the unit in at least STARTUP wi in the next 6 hours, in at least HOT SHUTDOWN within the following 6 hours a in at least COLD SHUT 00VN within the subsequent 24 hours. As a further exa le, ecification 3.6.7.1 requires two primary containrMnt hydrogen recombi r syst s to be OPERABLE and provides , explicit ACTION .equirements if on recombine system is inoperable. Under the requirements of Specification .0.3, if bot. of the required systems are inoperable, within one hour mea res must be ini ated to place the unit in at least STARTUP within the next hours and in at le st HOT SHUT 00WN within the following 6 hours. - 3.0.4 This specific tion provides that entry into an OPERATIONAL CONDITION must be made th (a) the full complement of r uired systems, equipment or component OPERABLE and (b) all other paramet rs as specified in the Limiting Conditi s for Operation being met without reg d for allowable deviations and out f service provisions contained in the AC ON statements. The intent f this provision is to ensure that unit operati n is not initiated with ither required equipment or systems inoperable or ther limits being exceede . Excep ions to this provision have been provided for a limited nu er V specific ions when startup with inoperable equipment would not affect ' o safety. These exceptions are stated in the ACTION statements of the
- l. _- appro iate specifications.
p AND GULF-UNIT 1 B 3/4 0-1
ML M +o t MPLICABILITY BA x /
\
4.0. This specification provides that surveillance activities nece ary to ensure e limiting Conditions for Operation are met and will be perf med during the 0 RATIONAL CONDITIONS or other conditions for which the Li ting
' nditicns for Operation are applicable. Provisions for additional s veillance
..tivities to b performed without regard to the applicable OPERATIO AL CONDI-TIONS or other co itions are provided in the individual Surveilla e Requirements. Sur 111ance Requirements for Special Test Excepti ns need only be performed when th Special Test Exception is being utilized an exception to an individual speci ication.
4.0.2 The provision of this specification provide al wable tolerances for performing surveillance activities beyond those specif ed in the nominal surveillance interval. Thes tolerances are necessary t provide operational flexibility because 9f schedul g and performance consi erations. The phrase "at least" associcced with a sur eillance frequency d s not negate this allowable tolarance; instead, it rmits the more fr quent performance of surveillance activities. The tolerance values, taken eithe individ lly or consecutively over 3 test intervals, are sufficiently restr' tive o ensure that the reliability associated with the surveillance activity 's ot significantly degraded beyond that obtained from the nominal specified in rval. 4.0.3 The provisions of this speci catio set forth the criteria for determination of compliance with the OP ABILITY equirements of the Limiting Conditions for Operation. Under this riteria, eq ipment, systems or components areassumedtobeOPERABLEiftheasfciatedsurvei ance activities have been satisfactorily performed within th specified time in rval. Nothing in this provision is to be construed as d ining equipment, sys ms or components OPERABt.E, when such items are to nd or known to be inope ble although still meeting the Surveillance Requir ments. 4.0.4 This specificati n ensures that surveillance acti "ties associated with a Limiting Conditions or Operation have been performed wi in the specified time interval prior to e ry into an applicable OPERATIONAL COND ION or other specified applicability ondition. The intent of this provision i to ensure that :urveillance acti ities have been satisfactorily demonstrated o a current basis as required to eet the OPERABILITY requirements of the Limiting Condition for Operation. Under the t ms of this specification, for example, during initial pla t startup or foll ing extended plant outage, the applicable surveillance acti ities must be erformed within the stated surveillance interval prior to placi or. returning he system or equipment into OPERABLE status.
.AND GULF-UNIT 1 B 3/4 0-2
ML SS-ol PIB NPPLICABILITY E BA
/
4.0.5 is specification ensures that inservice inspection of ASME de Class 1, 2 and components and inservice testing of ASME Code Class 1, and 3 pumps and valve will be performed in accordance with a periodically pdated version of Section of the ASME Boiler and Pressure Vessel Code and ddenda as required by 10 CFR 0, Section 50.55a. Relief from any of the ab ve require-ments has been provided ' writing by the Commission and is not a rt of these Technical Specific &tions. This specification include a clarification of the freque cies of perform-ing the inservice inspection and sting activities required y Section XI of the ASME Boiler and Pressure Vessel de and applicable Add da. This clarifi-cation is provided to ensure consisten in surveillu ' .tervals throughout these Technical Specifications and to re., ve any ambig
- es relative to the frequencies for performing the required ins vice inspe ion and testing activ-ities.
Under the terms of this specification, the mo restrictive requirements of the Technical Specifications take precedence o r e ASME Boiler and Pressure Vessel Code and applicable Addenda. For example the r uirements of Specifi-cation 4.0.4 to perform surveillance activitie prior to try into an OPERATIONAL CONDITION or other specified applicability co dition takes cedence over_the ASME Boiler and Pressure Vessel Code provis n which allows pui s to be tested up to one week after return to normal oper ion. And for exampl the Technical Specification definition of OPERABLE does not grant a grace period fore a device that is not capable of performin its specified function is dm. ared inoperable and takes precedence over e ASME Boiler and Pressure Vesse rovi-sion which allows a valve to be inca ble of performing its specified func 'on for up to 24 hours before being dec ared inoperable. I AND GULF-UNIT 1 B 3/4 0-3
Ph ( NL. S ol
" ~
3/4.0 APPLICABILITY BASES Specifications 3.0.1 through 3.0.4 establish the general requirements applicable to Limiting conditions for Operation. These requirements are based on the requirements for Limiting (Conditions for Operation stated in the Code of Fe Regulations,10CFR50.36c)(2):
"Limiting conditions for operation are the lowest functional capability or perfonnance levels of equipment required for safe operation of the facility, k' hen a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specification until the condition can be met."
Specification 3.0.1_ establishes the Applicability statement within each individual specification as the requirement for when i.e. , in which OPERATIONAL CONDITIONS or other specified conditions)(conformance t Limiting Conditions for Operation is required for safe operation of the facility. The ACTION requirements establish those remedial measures that must be taken within specified time limits when the requirements of a Limiting Condition for Operation are not met. It is not intended that the shutdown ACTION requirements be used as an operational convenience which permits (routine) voluntary removal of a system (s) or com[onent(s) from service in lieu of other alternatives that would not result in redundant systems or components being inoperable. There are two basic types of ACTION requirements. The first specifies the remedial measures that sermit continued operation of the facility which is not further restricted by t1e time limits of the ACTION requirements. In this case, conformance to the ACTION requirements provides an acceptable level of I safety for unlimited continued operation as long as the ACTION requirements ! continue to be met. The second type of ACTION requirement specifies a time limit in which conformance to the conditions of the Limiting Condition for Operation must be met. This time limit is the allowable outage time to restore an inoperable system or component to OPERABLE status or for restoring parameters within specified limits. If these actions are not completed within the allowabit outage time limit:,, a shutdown is required to place the facility in an OPERATIONAL CONDITION or other specified condition in which the specification no longer applies. The specified time limits of the ACTION requirements are applicable from the point in time it is identified that a Limiting Condition for Operation is not met. The time limits of the ACTION requirements are also applicable when a system or component is removed from service for surveillance testing of-investigation of operational p-oblems. Individual specifications may include i a specified time limit for the completion of a Surveillance Requirement when GRAND GULF-UNIT 1 B 3/4 0-1 A m m eur A . _ _. l
y b!L M ol 3/4.0 APPLICARILITY , BASES (Con't) equipment is removed from service. In this case, the allowable outage time linits of the ACTION requirements are applicable when this limit expires if the surveillance has not been completed. When a shutdown is required to comply with ACTION requirements, the plant may have entered an OPERATIONAL CONDITION in which a new specification becomes applicable. In this case, the time limits of the ACTION recuirements'would apply from the point in time that the new yecification becomes aprlicable if the requirements of the limiting Condition for Operation are not met. Saecification 3.0.2 establishes that noncompliance with a specification exists w1en the requirements of the Limiting Condition for Operation are not met and the associated ACTION requirements have not been implemented within the specified time interval. The purpose of this specification is to clarify that (1) implementation of the ACTION requirements within the specified time interval constitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not required when compliance with a Limiting Condition of Operation is restored within the time interval specified in the associated ACTION requirements. oieh Specification 3.0.3 establishes the shutdown ACTION requirements'that must be implemented when a Limiting Condition for Operatio is not met and the conditim is not specifically addressed by the ass ciated ACTION requirements. The pu p se of this specification is to delineate he time limits for placing the unit in a safe shutdown CONDITION when plant peration cannot be maintained within the limits for safe operation eTined by the Limiting Conditions for Operation and its ACTION require nts. It is not intended to be used as an operational convenience which pe its (routine) voluntary removal of redundant systems or components from servic in lieu of other alternatives that would not result in redundant systems or ent+ being inoperable. One hour is allowed to prepare for an orderly shutdown before initiating a change in plant operation. This time pemits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lower CONDITIONS of operation pemit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minimum required equipment is OPERABLE. This reduces thermal stresses on components of the primary coolant system and the potential for a plant upset that could challenge safety systems under conditions for which this specification applies. If remedial measures pemitting limited continued operation of the facility l under the provisions of the ACTION requirements are completed, the shutdown may be teminated. The time limits of the ACTION requirements are applicable . l from the point in time;there was a failure to meet a limiting Condition for j Operation. Therefore, the shutdown may be teminated if the ACTION < requirements have been met or the tine limits of the ACTION requirements hsve not expired, thus provi iing an allowance for the completion of the required actions. {
\
GRAND GULF-UNIT 1 B 3/4 0-2 brawur R. i
t4 L S b u as 3/4.0 APPLICABILITY BASES (Con't) The time limits of Specification 3.0.3 allow 37 hours for the plant to be in COLD SHUTDOWN when a shutdown is required during POWER operation. If the plant is in a lower CONDITION of operation whw a shutdown is required, the time limit for reaching the next lower CONDITION of operation applies. However, if a lower CONDITION of operation is reached in less time than allowed, the total allowable time to reach COLD SHUTDOWN, or other OPERATIONAL CONDITION, is not reduced. For example, if STARTUP is reached in 2 hours, the time allowed to reach HOT SHUTDOWN is the next 11 hours because the total time to reach HOT SHUTDOWN is not reduced from the allowable limit of 13 hours. - Therefore, if remedial measures are completed that would pennit a return to POWER operation, a penalty is not incurred by having to reach a lower CONDITION of operation in the total time allowed The same principle a lies ~with~ regard to the allow ION le ou age time limits of the ACTION requir nts, if compliance with the A requirements for ene f specification res ts in entry into an OPERATION CONDITION or condition of operation for :r...her specification in which th requirements of the Limiting Condition for Operation are not met. If the specification becomes applicable in less time than :;p/xifid, the differene may n. be added th: Me::ver, to the allowable
. %, u m ott&ge mii+,ma tinne +4limits m 34 e/r4+, arvenu .m-i,4.-+,the second specificat
< . 64 m . enunevenu .<.
m 4 & a teenA h [nv+n a 1 ist na +4 s 4 _ 5hiI55ie da[5 SI5Id:M I_54Ar - _ 75r'6p5Y55i5r M 5t 355 C 5 iEwer C0"DIT!0u er eper3tter, The shutdown requirements of Specification 3.0.3 do not apply in CONDITIONS 4 and S, because the ACTION reouf rements of individual specifications define the remedial measures to be taken. Specifi -* ion 3.0.4 establishes limitations en a change in OPERATIONAL CONDI' " en a Limiting Condition for Operation is not met. It precludes placi- e facility in a higher CONDITION of operation when the requirements for a t.imiting Condition for Operation are not met and continued noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements if a change in CONDITIONS were permitted. The purpose of this specification is to ensure that facility operation is not initiated or that higher CONDITIONS of operation are not entered when corrective action is being taken to obtain compliance with a specification by restoring equipment to OPERABLE status or parameters to specified limits. Compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a change in OPERATIONAL CONDITIONS. Therefore, in this case, entry into an OPERATIONAL CONDITION or other specified condition may be made in accordance with the provisions of the ACTION requirements. The provisions of this specification should not, however, be interpreted as endorsing the failure to exercise-good practice in restoring systems or components to OPEPABLE status before plant startup. GRAND GULF-UNIT 1 B 3/4 0-3 Awoomut A. c . - .
~NL 119-ol '
MS :l l INSERT 1 - was-required by the initial-ACTION requirements j 1 Y 1 INSERT 2 between the actual and the required time to reach the applicability of the second specification i ' [ l 1 1 [ l J16 MISC 88080201 - 1 ,
g .o; NO
. l 3/4.0 APPLICABILITY BASE {(Con't) 1 When a shutdown is required to cogly -with ACTION requirements, the provisions of Specification 3.0.4 do not apply because they would delay placing the l facility in a lower CONDITION of operation.
Specifications 4.0.1 through 4.0.5 establish the general requirements applicable to Surveillance Squirements. These requirements are based on the l Surveillance Requirements .P,ated in the Code of Federal Regulations, 10CFR50.36(c)(3):
"Surveillance reqti.ements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components is mainta N d, that facility operation will be within safety limits, and that the limiting conditions of operation will be met."
Specification 4.0.1 establishes the requirement that surveillances must be performed during Yne OPERATIONAL CONDITIONS or other conditions for which the requirements of the Limiting Coiditions for Operation apply unless otherwise stated in an individual Surveillance Requirement. The purpose of this specification is to ensure that surveillances are perforined to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in an OPERATIONAL CONDITION or other specified condition for which the individual Limiting ';onditions for Operation are applicable. Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL CONDITION for which the requirements of the associated Limipng Condition for Operation do not apply unless otherwise specified. The Surveillance Reautrements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a specification. Specification 4.0.2 establishes the conditions under which the specified time
'i nterval for Surveillance Requirements may be extended. Item a. permits an allowable extension of the nomal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient
~
conditions or other ongoing surveillance or maintenance activities. Item b. limits the use of the provisions of item a. to ensure that it is not used repeatedly to extend the surveillance interval beyond that specified. The e limits of Specification 4.0.2 are based on engineering judgment and the recognition that_ the most probable result of any particular surveillance being . perfomed is the verification of conformance with the Surveillance Requirements. These provisions are sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond , that obtained from the specified surveillance interval. Specification 4.0.3 establishes the failure to perfom a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure GRAND GULF-UNIT 1 B 3/4 0-4 A % e,,r A. , f
~
^ NL Sbol RH l l 3/4.0 APPLICABILITY ) BASES (Con't) ) to meet the OPERABILITY reouirements for a Limiting Condition for Operation. I Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval. However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements. This specification also clarifies that the ACTION requirements are applicable when Surveillance Recuirements have not been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in time it is identified that a surveillance has not been perfomed and not at the time that the allowed surveillance interval was exceeded. Completion of the Surveillance Requirement within the allowable out' age time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3. However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action. Further, the failure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73(a)(2)(1)(B) because it is a condition prohibited by the plant's Technical Specifications. If the allowable outage time limits of the ACTION requirements are less than 24 hours or a shutdown is required to comply with ACTION requirements, e.g., Specification 3.0.3., a 24-hour allowance is provided to permit a delay in implementing the ACTION requirements. This provides an adequate tima limit to complete Surveillance Requirements that have not been performed. The purpose of this allowance is to permit the completion of a surveillance before a shutdown would be required to comply with ACTION requirements or before othsr remedial measures would be required that may preclude the completion of a surveillance. The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perfonn the surveillance, and the safety significance of the delay in completing the required surveillance. This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of CONDITION changes imposed by ACTION requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of Specification - 4.0.4 is allowed. If a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time. When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is teminated. Surveillance Requirements do not have to be perfomed on inoperable equipment because the ACTION requirements define the remedial meatures that apply. " However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPEPABLE status. GRAND GULF-UNIT 1 B 3/4 0-5 A cuemem A.
< ~ NL SS ol 3/4.0 APPLICABILITY BASES (Con't) , 1 Specification 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL CONDITION or other condition of operation specified in the Applicability statement. The purpose of this specification is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into an OPERATIONAL CONDITION or other specified condition for which these systems and components ensure safe operation of the facility. This provision applies to changes in OPERATIONAL CONDITIONS or other specified conditions associated with plant shutdown as well as startup. , 1 Under the provisions of this specification, the applicable Surveillance ; Requirements must be performed within the specified surveillance interval to assume that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage. When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower CONDITION of operation. Specification 4.0.5 establishes the requirement that inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shail be performed in accordance with a periodically updated version of Section XI of the ASME Roiler and Pressure Yessel Code and Addenda as required by 10 CFR 50.55a. These requirements apply except when relief has been provided in writing by.the Comission. This spccification includes a clarification of the frequencies for perfoming the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Yessel Code and applicable Addenda. This clarification is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for perfoming the required inservice inspection and testing activities. Ilnder the tems of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Yessel Code and applicable Addenda. The requirements of Specification 4.0.4 to perfom surveillance activities before entry into an OPERATIONAL CONDITION or other specified condition takes precedence over the ASME Boiler and Pressure Yessel Code provision that allows pumps ed 9/c: to be tested up to one week after return to nomal operation. The Technical Specification definition of OPERABLE does not allow a grace period before a component, which is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision - that allows a valve to be incapable of perfoming its specified function for up to 24 hours before being declared inoperable. GRAND GULF-UNIT 1 B 3/4 0-6 hourm No.}}