Text

Forwards Changes to Final Draft Tech Specs,Per Meetings W/ NRC During Wk of 850128.Change to Table 3.6-1 Re Containment Isolation Valves Originally Submitted by Resubmitted to Clarify Request
	ML20101T405
Person / Time
Site:	Wolf Creek
Issue date:	02/01/1985
From:	Petrick N; STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM
To:	Harold Denton; Office of Nuclear Reactor Regulation
References
	SLNRC-85-5, NUDOCS 8502060148
	Download: ML20101T405 (15)
	v • d • e

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SNUPPS Standardized Nuclear Unit Pouver Plant System 5 Choke Cherry Road Nicholas A.Petrick v land 20s50 Executive Director February 1,1985 SLNRC 85-5 FILE: 0543 SUBJ: Wolf Creek Technical Specifications Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket No. STN 50-482 Refs: 1) KGE (G. L. Koester) letter to NRC (H. R. Denton), dated 12/10/84, Same Subject

2) NRC (D. G. Eisenhut) letter to KGE (G. L. Koester), dated 11/7/84, Same Subject

3) SLNRC 85-2, 1/18/85, Same Subject

4) SLNRC 85-04, 1/25/85, Same Subject

Dear Mr. Denton:

Reference 1 forwarded KGE's comments on the Final Draft version of Wolf Creek's Technical Specifications as issued by reference 2. Since reference 1, several other changes have been identified which were forwarded with reference 3, 4 and this letter. The changes contained herein were discussed with members of your staff in meetings during the week of January 28, 1985. In addition, the change to Table 3.6-1 (containment isolation valves) which was originally submitted in Reference 3 is resubmitted herein in order to clarify our request. Very uly yours,

                                                                 \ {M%E Nicholas A. Petrick JHR/bds/6a10 Attachments cc:    G. L. Koester               KGE J. M. Evans                 KCPL D. F. Schnell               UE J. Neisler/B. Little        USNRC/ CAL H. Bundy                    USNRC/WC             .

W. L. Forney USNRC/RIII D. R. Hunter USNRC/RIV Y YO po\ l s i

s TABLE 2.2-1 8 REACTOR TRIP SYSTEN INSTRWENTATION TRIP SETPOINTS n . SENSOR R TOTAL ERROR E FUNCTIONAL UNIT ALLOWANCE (TA) Z' (S) TRIP SETPOINT ALLOWA8LE VALUE

1. Manual Reactor Trip N.A. -N.A. N.A. N.A. M.A.

E Z 2. Power Range, Neutron Flux g a. High Setpoint 7. 5 4.56 0 $109% of RTP* $112.3% of RTP*

b. Low Setpoint .8.3 4.56 0 125% of RTP* 128.3% of RTP*

3. Power Range, Neutron Flux, 2.4 0.5 0 High Positive Rate 54% of RTP* with 16.3% of RTP" with

                                                                                   - a time constant
                                                                                                       - a-time constant 12 seconds            12 seconds          .

4. Power Range, Neutron Flux, 2.4 0.5 0 <4% of RTP* with High Negative Rate <6.3% of RTP* with a time constant a ti'ae constant m

1

12 seconds 12 seconds

5. Intermediate Range, 17.0 8.41 0 Neutron Flux l'5

                                                                             '      $25% of RTP"          $35.3% of RTP*    .

I I

6. Source Range, Neutron Flux 17.0 10.01 n. - os cps $1.6 x 105 cps

v. t. 3,% .73.* e 67

7. Overtemperature AT hrt 4:43 4-96 ee Note 1 See Note 2

" o.: e,

8. Overpower AT 5.5 1.43 triMir See Note 3 See Note 4

9. Pressurizer Pressuie-Low 3.7 0.71 2.49 11875 psig 11866 psig

. 10. Pressurizer Pressure-High 7.5 0.71 2.49 12385 psig 12400 psig

11. Pressurizer Water Level-High 8.0 2.18 1. % $92% of instrument 193.9% of instrument span span

     *RTP = RATED THERMAL POWER
     ** Loop design flow = 95,700 gpm

~

I

                                                                      . JA8tE 2.2-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS , 52 SENSOR N; TOTAL , ERROR [ , FUNCTIONAL UNIT ALLOWANCE (TA)41 (S) TRIP SETPOINT 19-) LLOWABLE VALUE l c- 12. Reactor Coolant Flow-Low 4. -77 i 0.6 >90% of loop > h ) f loop g 25 3LI ;Lct7 design flow ** design flow"*

          .     -4

13. Steam Generator Water 23.5 21.18 2.51 >23.5% of narrow >22.3% of narrow Level Low-Low range instrument range instrument

 .                                                                                                     span                      span
 ,                      14. Undervoltage - Reactor             7.5                 1.3         0
                                                                                                       >10578 Volts A.C.         >10355 Volts A.C.

Coolant Pumps

15. Underfrequency - Reactor 3.3 0 0 >57.2 Hz >57.1 Nz

n. Coolant Pumps E

16. Turbine Trip i $se. co $~.s f.s o

a. Low Fluid Oil Pressure N.A. M.A. ,jN.A. >SSR=Ge psig .3 %.7T,psig

b. Turbine Stop Valve N.A. M.A.I l' N.A. >1% open >1% open Closure .

17. Safety Injection Input N.A. lN.A. :N.A. N.A. N.A.

from ESF. O g h 4

F

                                                                                                                         ._.           ..-_ ~

o E TABLE 2.2-1 (Continued) ' q; n TABLE NOTATIONS (Continued) R NOTE 1: (Continued) y Reiereme-

       ,                            T' c                                             = @ 588.S*F (ieo=+nel T,yg at RATED TilERMAL POWER);                        ,

K3 = 0.000671; W -{ H sma P = . Pressurizer pressure, psig; E P' = 2235 psig (Nominal RCS operating pressure); P S = Laplace transform operator, s 8; and f (a!) is a function of the indicated difference between top and bottom detectors of the N power-range neutron ion chambers; with gains to be selected based on measured instrument u response during plant STARTUP tests such that:

 . cm (1) for q t      gbbetween -35% and + 7%, f (al) = 0, where q and qb are Percent 3

M RATED THERMAL POWER in the top and bottom halves of the core respectively..and qg+qb IS tot 41 TilERMAL POWER in percent of RATED THERMAL POWER; e (ii) for each percent that the magnitude of q qbexceeds -35%, the AT Trip Setpoint shall be automatically reduced by 1.26% of its value at RATED THERMAL POWER; and (iii) for each percent that the magnitude of q gbexceeds +7%, the AT Trip setpoint shall be automatically reduced by 1.05% of its value at RATED TilERMAL POWER. NOTE 2:

                           -hannel's of AT span. maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than

TABLE 2.2-1 (Continued) E q TABLE NOTATIONS (Continued) Q 899 NOTE 3: (Continued) 7 K. = 0.00128/*F for T > T" and K = 0 for T $ I"; E T =

     -e                                    Average temperature, *F; T"        =

Indicated T,,g at RATED THERMAL POWER (Calibration temperature for AT instrumentation, 5 588.5*F); 5 = Laplace transform operator, s 1; and f 2(al) = 0 for all al. NOTE 4: - y Jr5% annel's f AT span.maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than g %s

                                                                                                                   '+d 32w g,-

WJ Tb m M

POWER OISTRIBUTION LIMITS FBAb1 Ma A F T 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LIMITING CONDITION FOR OPERATION 3.2.3 The combination of indicated Reactor Coolant System (RCS) total flow rate and R shall be maintained within the region of allowable operation shown on Figure 3.2-3 for four loop operation. Where: N F aH

a.

R = 1.49 (1.0 + 0.2 (1.0 - P)]

b* P THERMAL POWER , and

                        = RATED THERMAL POWER

c. Fh=MeasuredvaluesofFhobtainedbyusingthemovableincore detectors to obtain a power distribution map. The measured valuesofFhshallbeusedtocalcula since Figure 3.2-3 includes measurement uncertainties o .2A.% f r flow and 4%

for incere measurement of F N .

#*T

APPLICABILITY: MODE 1.

ACTION: With the comoination of RCS total flow rate and R outside the region of acceotsole coeration snown on Figure 3.2-3:

a. Within 2 hours either:

1. Restore the combination of RCS ,,tal flow rate and R to within the aoove limits, or

2. Reduce THERMAL POWER to less than 52% of RATED THERMAL POWER an reduce the Power Range Neutron Flux - Hign Trip Setpoint to less than or equal to 55% of RATF0 THERMAL POWER within the next 4 hours,

b. Within 24 hours of initially being outside the above limits, ve..fy througn incore flux mapping and RCS total flow rate comparison that the combination of R and RCS total flow rate are restored to within the above limits, or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours; and WOLF CREEK . UNIT 1 3/4 2-8 -

m

   ,                                      e,

[S.T MEASUREMENT UNCERTAINTIES C F 4.0% FOR INCORE MEASUREMENT F F c AREINCLUDED

FOR FLOW AND

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p opcA Af/e4 REGICA) i

9 , _ - ~~~' ACCEPTA8LE - UNACCEPTABLE l ; OPERATION OPERATION M

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34 - ' - - - - - - - -- - + - - - - - - - - - - 0.90 0.95 1.00 1.05 , 1.10 R = Fj/1.49(1.0 + 0.2(1.0 PQ FIGURE 3.2-3 RCS TOTAL FLOW RATE VERSUS R FOUR LOOPS IN OPERATION WOLF CREEK - UNIT 1 3/4 2-9 .

FMA!. DNT TA8LE 3.6-1 (Continued) CONTAINMENT ISOLATION VALVES MAXIMUM TYPE LEAK ISOLATION TI PENETRATIONS VALVE NUMBER FUNCTION TEST REQUIRE 0 (Seconds) _

8. Hand-Operated and Check Valves - (Continued)

P-66 EN V-017 CTMT Spray Pump 8 A N.A. to CTMT Spray Nozzles P-45 EP V-046 Accumulator Nitrogen C N.A. Supply Line P-43 HD V-016 Auxiliary Steam to C N.A. Decon System P-43 HD V-017 Auxiliary Steam to C N.A. Decon System P-63 KA V-039 Rx Bldg Service Air C N.A. Supply P-63 KA V-118 Rx Bldg Service Air C N.A. Supply P-98 KB V-001 Breathing Air Supply C N.A. to RX Bldg P-98 KB V-002 Breathing Air Supply C N.A. to RX Bldg P-30 KA V-204 Rx Bldg Instrument C N.A. Air Supply P-67 KC V-478 Fire Protection C N.A. Supply to RX Bldg P-57 SJ V-111 Liquid Sample from A,C N.A. PASS to RCOT

9. Other Automatic Valves P-1 AB-HV-11*** lin. Stm. Isol. A 5 NA P-2 A8-HV-14**4 Mn. Stm. Isol. A 5 da P-3 A8-HV-17*** Mn Stm. Isol. A 5NA

         **The provisions of Specification 3.0.4 are not applicable.
      , en e

%O WOLF CREEK - UNIT 1 3/4 6-29 a saws

FlK.DNFT TABLE 3.6-1 (Continued) CONTAINMENT ISOLATION VALVES MAXIMUM TYPE LEAK ISOLATION TI PENETRATIONS VALVE NUMBER FUNCTION TEST REQUIRED (Seconds) ,_

9. Other Automatic Valves (Continued)

P-4 AB-HV-20*** Mn. Stm. Isol. A VA P-5 AE-FV-42*** Mn. FW Isol. A 5NA P-6 AE-FV-398** Mn. FW Isol. A 14A P-7 AE-FV-40*** Mn. FW Isol. A ENA P-8 AE-FV-41**

Mn FW Isol. A idA P-9 BM-HV-4** SG Blowdn. Isol. A 10 P-10 BM-HV-1** SG Blowdn. Isol. A 10 P-11 BM-HV-2** SG Blowdn. Isol. A 10 P-12 BM-HV-3** SG Blowdn. Isol. A 10

 ,,,     wg        g g , < =. w:.Wded fw ta ble. o m pettness , N re pice s.,g of speci 6 bon 16 5 4 not oPPly ) '

5 tea d % retu" w nt.s

                                                                                        *f
                                      ,,a    speu b ben       3.32,   opgy   % tw. c%,

spec.sq u ben 17. i . s rs.t t. ion Wim ona % Fe edwa tes. rs,(,wn 4( ge,3 ,

           %am fa s pecbw ty.
    **The provisions of Specification 3.0.4 are not applicable.

WOLF CREEK - UNIT 1 3/4 6-30 >

1 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

c. At .least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communicating with the system by:

1) Verifying that the Control Room Emergency Venttlation System satisfies the in place penetration and bypass leakage testing acceptance criteria; of less than 1% for HEPA filters and 0.05%

for charcoal adsorbers and uses the test procedure guidance in Regulatory Positions C.5.a. C.5.c, and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 2000 cfm +3, -05 at greater than or equal to 6.6 inches Water Gauge (W.G.) (dirty filter) for the Filtration System and 2200 cfm +3, -0% at greater than or equal to 3.8 inches W.G. - (dirty filter) for the Pressurization System with 500 cfm +3,

                          -0% going through the Pressurization System filter adsorber unit;

2) Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than

                  .1%     W , and

3) Verifying system flow rate of 2000 cfm +3, -0% at greater than or equal to 6.6 inches W.G. (dirty filter) for the Filtration System and 2200 cfm +3, -0% at greater than or equal to 3.8 inches W.G. (dirty filter) for the Pressurization System with 500 cfm +3, -0% going through the Pressurization System filter adsorber unit during system operation when tested in accordance with ANSI N510-1980.

d. After every 720 hours of charcoal adsorber operation by verifying within 31 days after removal, that a laboratory analysis of a represen-tative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than.0,05%;

t%

e. At least once per 18 months by:

1) Verifying that the pressure drop across the combined HEPA filters and charcoal adsorb'r e banks is less than 6.6 inches Water Gauge while~ operating the system at a flow rate of 2000 cfm

                          +3, -0% for the Filtration System and 500 cfm +3, -0% for the Pressurization System filter adsorber unit,

2) Verifying that on a Control Room Ventilation Isolation or High Gaseous Radioactivity test signal, the system' automatically switches 'into a recirculation mode of operation with flow through the HEPA filters and charcoal adsorber banks, WOLF CREEK - UNIT 1 3/4'7-15 -

C

I~ i PLANT SYSTENS 3/4.7.7 EMERGENCY EXHAUST SYSTEM f LIMITING CONDITION FOR OPERATION i J

   -                 3.7.7 Two independent Emergency Exhaust Systems shall be OPERA 8LE.

APPLICA8ILITY: MODES 1, 2, 3, and 4.

l ACTION: $ With one Emergency Exhaust System inoperible, restore the inoperable Emergency Exhaust System to OPERABLE status within 7 days or be in at least HOT STAN08Y within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. 1-j SURVEILLANCE REQUIREMENTS p 4 ! 4.7.7 Each Emergency Exhaust System shall be demonstrated OPERA 8LE: 1 ! a. At least once per 31 days on a STAGGERED TEST BASIS by initiating, 3 + from the control room, flow through.the HEPA filters and charcoal L adsorbers and verifying that the system operates for at least - 10 continuous hours with the heaters operating; 4- b. At least once per 18 months, or (1) after any structural maintenance , 4 . on the HEPA filter or charcoal adsorber housings .or (2) following painting, fire, or chemical. release in any ventilation zone communicating with the system, by: l 1) Verifying that the Emergency Exhaust System satisfies the in-l' place penetration and bypass leakage testing acceptance cri-teria of less than 1% for HEPA filters and 0.05% for charcoal adsorbers and uses the test procedure guidance in Regulatory Positions C.5.a C.5.c, and C.5.d of Regulatory Guide 1.52, i Revision 2, March 1978, and the system flow rate is-9000 cfm

                                            +3, -05 at > 7.2 inches W.G. (dirty filter);

2) Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance f with Regulatory Position C.6.b of Regulatory Guide 1.52, f Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide'1.52, Revision 2, i- March 1978, for a methyl iodide penetration ~of less than &4HR',

I 'l. i , WOLF CREEK - UNIT 1 3/4.7-17 -

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

3) Verifying a system flow rate of 9000 cfm +3, -0% at > 7.2 inches W.G. (dirty filter) during system operation when tested in accordance with ANSI N510-1980.

c. After every 720 hours of c'harcoal adsorber operation, by verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl

iodide penetration of less than 0,69%;

t%

d. At least once per 18 months by:

1) Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks of less than or equal to

, 7.2 inches Water Gauge while operating the system at a flow rate of 9000 cfm +3, -0%,.

2) Verifying that the system maintains the Fuel Building at a negative pressure of greater than or equal to % inch Water Gauge relative to the outside atmosphere during system operation, f: 3) Verifying that the system starts on a Safety Injection test signal, and; 4) Verifying that the heaters dissipate 37 1 3 kW when tested in a accordance with ANSI N510-1975.

! e. After each complete or partial replacement of a HEPA filter bank, by . verifying that the cleanup system satisfies the in place penetration and bypass leakage testing criteria of less than 1% for HEPA filters and 0.05% for charcoal adsorbers in accordance with ANSI N510-1975 (however Prerequisite Testing, Sections 8 and 9 shall be in accordance with ANSI N510-1980) for a DOP test aerosol while operating the system at a flow rate of 9000 cfm +3, -0%; and

f. After each complete or partial replacement.of a charcoal adsorber

bank, by verifyi.ng that the cleanup system satisfies the in place penetration'and bypass leakage testing criteria of less than 1% for HEPA filters and 0.05% for charcoal adsorbers in accordance with ANSI N510-1975 (however Prerequisite Testing, Sections 8 and 9 shall

be in accordance with ANSI N510-1980) for'a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of i 9000 cfm +3, -0%. , , ~- . . . - . . . . . . WOLF CREEK - UNIT 1 3/4 7-18 )

4

                      ,            . s                     -

REFUELING CPERATIONS ,. N* SURVEILLANCE REQUIREMENTS (Centinued)

2) Verifying, within 31 da after removal, that,a laboratory analy-sis of a representativ carbon sample otetained in accordance with

      . , , , , .,                   Regulatory Position .6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets ' e laboratory testing criteria of Regulatory Position C.6.= " wulatory Guide 1.52, Revis'                             , March 1978, for a methyl                     enetration of less than               ; and        .

3) Verifying a system flow rate of 9000 cfm +3, -

                                                                                                             >_ 7.2 inches W.G. (dirty filter) during system operation when tested in accordance with ANSI N510-1980.

c. After every 720 hours of charcoal adsorber cperation, by verifying, within 31 days after removal, that a laboratory analysis of a repre- -

                            'sentative carbon sample obtained in accordance with Regulatory Posi-                                  l tion C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the                               j laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of                                l less than 1%;

d. At least once per 18 months by: l

1) Verif,'ng that the pressure drop across the corbined HEPA !

filters and charcoal adsorber banks is less than or equal to ; 7.2 inches Water Gauge while operating the system at a flow rate ' of 9000 cfm +3, -0%. hd

2) Verifying that on a Sg -t 1.C :: ' Gaseous Radioactivity-High test signal, the system automatically starts (unless already operating) and directs its exhaust flos through t'e HEPA filters 1.c c.arccal adsorber banks anc isolates the n:rrai fuel building

                                     + e wit :- to the auxiliary / fuel building eesust fan; 3~        srif,#r; - net .Pa siste.' r.aintains tne :_e E i M'ng at a r.ega-
                                      .i.E :xessu e of graater t',ar, or ecua' to If

inc Es Water Gauge -

                                        . ~ .t i . e t , P e c   r i de a t a s ,.,. :- e u. ' T r. 5 .t.T ;;- a;icq; EN

4) verifying t .at the heaters dissipate 37 : 3 kW wrar tested in acc:rdance witn ANSI N510-1975.

                    ,   e. Af .er es:n cc.-f.ete or ;.artial replaceT.ent of a %EFA fi'ter bank, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% for HEPA filters and 0.05% for charcoal adsorbers ir accordance with ANSI N510-1975 (however Prerequisite Testing, Sections 8 and 9 shall be in accordance with ANSI N510-1980) for a DOP test aercsol while operating the system at a flow rate of 9000 cfm +3, -0%; and

f. After each complete or partial replacement of a charcoal adsorber t

bank, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% for HEPA filters and 0.05% for charcoal adscrters in accord-ance with ANSI N510-1975 (however Preraquisite Testing, Sections 8 and9shallbeinaccordancewithANSIN510-1980)forahalogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 9000 cfm +3, -0%. WOLF CREEK - UNIT 1. 3/4 9-18

FINAL MAFT e TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODE 1, 2, 3, or 4 MODE 5 or 6 SS 1 le SRO 1 None RO 2 1 50 4 1 STA 1** None CHM 1 None SS - Shift Supervisor with a Senior Operator license on Unit 1 SRO - Individual with a Senior Operator license on Unit 1 RO - Individual with an Operator license on Unit 1 50 - Station Operator STA - Shift Technical Advisor CHM - Chemistry Personnel The Shirt Crew Composition may be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the Shift Crew Composition to within the minimum requirements of Table 6.2-1. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent. During any absence of the Shift Supervisor from the control rocm while the unit is in MODE 1, 2, 3, or 4, an individual (other than the Shift Technical Advisor) with a valid Senior Operator license shall be designated to assume the control room command function. During any absence of the Shift Supervisor I from the control room while the Unit is in MODE 5 or 6, an individual with a valid Operator license (other than the Shift Technical Advisor) shall be designated to assume the control room command function. NThe STA position shall be manned in MODES 1, 2, 3, and 4 unless the Shift l Supervisor or the individual with a Senior Operator license meets the qualifications for the STA as required by the NRC. Shit Squvec or #*P o me. 540 CAh" 3 Sweer*sms E. WOLF CREEK - UNIT 1 6-5 _ __

O FINAL DMFT ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6.8.3 Changes to Procedures

a. Temporary changes to Major Procedures, of the categories listed in Specification 6.8.1 which do not change the intent or generate an unreviewed safety questica of the original or subsequent approved procedure, may be made provided such changes to operating procedures

[ are approved by the Shift Supervisor (SRO licensed) and one of the 1 Call Superintendents. For temporary changes to Major Procedures under the jurisdiction of Maintenance, Instrumentation and Control. Reactor Engineering, Chemistry, or Health Physics which do not change the l intent or generate an unreviewed safety question, changes may be made upon approval of the Cognizant Group Leader and a Call Superintendent.

All temporary changes to' Major Procedures (made by a Call Super-l intendent and either a Cognizant Group Leader or the Shift Supervisor)
shall subsequently be reviewed by the PSRC and approved by the Plant l Manager within 14 days, except that temporary changes to Major Pro-L cedures made during a refueling outage may be reviewed and approved l at any time prior to initial criticality of the reload core. All permanent changes to Major Procedures shall be made in accordance with Specification 6.8.2.a.

Opeed.ms

b. All temporary or permanent changes to MinortProcedures (checkoff lists, alarm responses, data sheets, operating instructions, etc.)

shall be approved by the Shift Supervisor, and shall be subsequently reviewed and approved by the Operations PSRC Subcommittee. All tem-l parary or permanent changes to other Minor Procedures under the jurisdiction of Maintenance, Instrumentation and Control, Reactor Engineering, Chemistry, or Health Physics, shall be approved by a Cognizant Group Leader and shall be subsequently reviewed and approved by the appropriate PSRC Subcommittee.

c. Temporary changes to Corporate Emergency Plan implementing procedures may be made provided that: (1) the intent of the original procedure is not altered, (2) the change is approved by the Emergency Planning Coordinator, and (3) the change is documented, reviewed by appropriate

' Corporate and plant personnel and approved by the Vice President-Nuclear within 14 days of the implementation. 6.8.4 The following programs shall be established, implemented, and maintained.

a. Reactor Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the appropriate portions of the Containment Spray System, Safety Injection System, Chemical and Volume Control System, RHR System, and the Nuclear Sampling Systema (PASS only). The program L ffinll imlud_e Gho follmiat.}}

ML20101T405

Text

Dear Mr. Denton:

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