ML20129D042

From kanterella
Jump to navigation Jump to search
Forwards Results of in-depth FSAR Commitment Compliance Review of Initial Startup Test Program.Documents Reviewed Include Fsar,Reg Guide 1.68 & SER
ML20129D042
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 01/10/1985
From: Koester G
KANSAS GAS & ELECTRIC CO.
To: Martin R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
RTR-REGGD-01.068, RTR-REGGD-1.068 KMLNRC-85-014, KMLNRC-85-14, NUDOCS 8507160402
Download: ML20129D042 (49)
v • d • e


Text

l c

,,g KANSAS GAS AND ELECTRIC COMPANY T>E ELECTRC COMPANY OLENN L MOESTER

..u m.m < ,.x a.. January 10, 1985 Mr. Robert D. Martin _.

Regional Administrator, Region IV } @ Q p~ g'g [;

U.S. Nuclear Regulatory Commission " g.

611 Ryan Plaza Drive, Suite 1000 / 1

- Arlington, Texas 76011 JAN I T 1985 4-KMLNRC 85-014 -

Re: Docket No. STN 50-482 KMLNRC 84-420, dated 12/31/84 from'

-~

Ref:

NRC _

Subj: GLKoester, FSAR KGSECompliance Commitment to RDMartin$tudy L :r Mr. Martin:

The Reference provided a report documenting the completion of the FSAR review activities associated with the Wolf Creek Preoperational Test Program. The Reference committed to the completion of a similar indepth commitment compliance review of the Initial Startup Test Program.

The attached report documents the results of this second review activity.

Yours very truly, ftl6 N Glenn L. Koester Vice President-Nuclear Attach GPR: dab xc: W. Guldemond H. Bundy P. O'Connor R.P. Denise i n, \

~

8507160402 050110 '

PDR ADOCK 05000402 A ppg th 201 N. Market -Wictuta. Kansas -Mail Address: PO. Box 208 I WicMa, Kansas 67201 - Telephone: Area Code (316) 261-6451

Attachment to KMLNRC 85-014

~~

foam 1177 aty, t.47 l INTEROFFICE CORRESPONDENCE i To: Gary D. Boyer FROM: William B. Norton DATE: January 8, 1985

SUBJECT:

Initial Startup Test Program Comitment/ Compliance Report i

! EMOLKWO 85-016 In order to ensure the WCGS Initial Startup Test Program complies with all the various comitments, an extensive review of the documents containing comitments has been performed. The results of this review are compiled in i

this report.

The following documents were reviewed to identify initial startup program comitments:

1) The FSAR excluding Chapters 1, 2, 13, 16 and 17. These chapters were excluded because they cover topics not associated with the startup test program.
2) Chapter 14 of the FSAR, which contains startup test abstracts, was reviewed line by line to identify each comitment.

j 3) The FSAR site addendum excluding the same chapters identified in (1) above.

4) Regulatory Guide 1.68.
5) Volume 11 of the FSAR (NRC Questions and Correspondence).

i

6) Safety Evaluation Report (SER) .
7) The preoperational test program FSAR commitment compliance report was

! also reviewed. The itms in the preop report with responsibility assigned to the initial startup program were included as comitments.

l The attached tables are a sumary of co mitments identified in the above l documents. Also included in these tables are the corresponding test

procedures that satisfy the comitment. An additional column entitled i

" NOTE" has been included for clarification: please refer to the Footnote table to identify the meaning of each number used in the column.

The WCGS procedures will be reviewed against the available companion Callaway procedures. Test change notices, test deficiencies and notes and

coments will be incorporated into WCGS procedures as appropriate. The l

procedures will also be revised to incorporate references to plant operating

procedures where deemed appropriate.

l

( -

    • ' n'OLKWO 85-016

January 8, 1985 Page 2 I {\h i William B. Norton Reactor Engineering Supervisor WBN/bss cc: F. Rhodes G. Boyer A

t iL A "

"w a

I L

\'

\

\

s 'g .

, s

' f1 '

. . < , ' ? '"

.. -... .. . . . , ~

..u_--. .- ' -' d*= ' ' 'a - G4

Notes and Jymbols t

The followirrg notes and abbreviations were used in compiling the following tables:

Document -

identifles the document and paragraph number where a comitment was found.

PG -

identifies what page in the above document where the comitment was located. ,

Type -

used to . identify the type of commitment for the test abstract review, such as OB for objectives, TI for title, AC for acceptance criteria, PR for preregs, TM for test mathod. Also need to identify nultiple comitments in the same paragraph number.

Comitment - - a 40 character paraphrase of the comitment found in the document identified above.

Procedure - identifies the procedure which meets or complies with the associated comitment.

Section(s) - ' identifies the section or step of a procedure which complies with the comitment.

Note -

identifies additional notes or coments about the comitment or compliance as shown in the Footnote table.

l

  • I er. ' =' S 4 -" A-

,j _f_ ,.

.,i e.>. Ja ,w.  % ~ JC -e m4*e w + - _.----a-++-M.--mi=**+.' ' i ~4 b **'A' 5

KG&E Pege1 FSAR TEXT 01/09/85 Document P0 TYPE COMilTMENT PROCEDURE SECTION(S) NOTE 10.0 CHAPTER 10 -- No Commitments 11.0 CH APTER 11 -- No Commitments 12.0 CHAPTER 12 12.3.4.1.2.6 22 Area rad monitors calibrated 8,33 14.0 CHAPTER 14 14.2.1 1 (1) Testing done in 3 phases. SU7-S000 1.1 14 2.1 1 (2) Preop testing prerequisite. SU7-S000 5.1 14.2.1.2 2a (a) Site fuelloading. SU7-0001 All 3 14.2.1.2 2a (b) Safe criticality. SU7-0002 All 3 14.2.1.2 3 (c) Low pvr testing confirms safety analysis ADM 01-070 42.2 3 14.2.1.2 3 (d) Safe power ascension tests. SU7-S008 A1 14.2.1.2 3 (e) Test transient & accident condiitons. ADM01-070 4.2.4 3 14.2.10.1 7 (1) Plant Supt. resp. for fuel load coord. ADM 05-600 4.1.1 14 2.10.1 7 (2a) Licensed SRO directs fuelload SU7-S009 4.1 14.2.10.1 7 (2b) SRO has no other responsibilities. SU7-S009 4.1 14.2.10.1 8 (1) Alternate core config. if appV. by Vest. SU7-0001 92.1 14.2.10.1 8 (2) Proc. specify boron concentration. SU7-S009 6.1.1 3 14 2.10.1 8 (3a) Procedure specifies safe fuel movement. SU7-0001 6.5 3 14.2.10.1 8 (4) Core loading conditions. SU7-0001 All 3 14 2.10.1 C (5b) Resp. for core component accountability. ADM 05-600 5.3.lb 14.2.10.1 8 (5c) Authority for fue1 accountability. ADM 05-600 4.1.4 3 14.2.10.1 8 (6) Containment structure /LRT complete. SU7-S008 5.1.1 14.2.10.1 8 (7) Fuel handling tools checked out. SU7-S009 5.9 1

1

KO&E pig 3 2 FSAR TEXT 01/09/85 Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE i 14.2.10.1 8 (0) Operators familiar v/ fuel handling equip 7 I

F 14.2.10.1 8 (9) Insp. of fuel assy, RCC A's & RV coinplete SU7-S009 5.15 14.2.10.1 8 (10) RV & components ready for fue1 receipt. SU7-S009 5.2 3 l

14.2.10.1 8 (11) Yater level above nozzle bottom SU7-S009 5.9 l

14.2.10.1 8 (12) Boron concent. ation can be increased. SU7-S009 4.4

, 14 2.10.1 8 (13) Fuelload stops when n count rate double SU7-S009 4.1.2 14.2.10.1 8 (14) Fuelload stop when CR inc. by 5 factor. SU7-S009 4.1.1 14.2.10.1 8 (15) Fuel load stop when boron cone -20 ppm. SU7-S009 4.1.3 14.2.10.1 0 (16) Load commences only after evaluation. SU7-S009 4.1 14 2.10.1 8 (17) Alarm in cont., CR from SR. SU7-S009 4.1.5 14.2.10.1 9 (1) High CR alarm,stop load until eyaluated. SU7-S009 4.1

, t42.10.1 9 (2) Core assembled in RV v/Keff ( 0.95. SU7-S909 4.4 1

14.2.10.1 9 (3) RV chemistry monitored during fuelload. SU7-S009 5.10 14.2.10.1 9 (4) Min. 2 sources in core to ensure 2 CPS. SU7-S009 4.1.8 I 14 2.10.1 9 (5) Perm. & temp. NIS SR used. SU7-SC01 All 3 f

14.2.10.1 9 (6) One perm. channel equipped v/ audio ind. SU7-0302 4.4 14.2.10.1 9 (7) One temporary channelon recorder. SU7-0001 3.1 14.2.10.1 9 (8) Min CR of 2 on 2/4 channels - fuelload SU7-S009 42 14.2.10.1 9 (9) Response check 8 hrs prior to core load. SU7-0001 4.14 14.2.10.1 9 (10) Response check 8 hrs before resump of FL. SU7-0001 4.14 14.2.10.1 9 (11) Load fuel assy individually in appy seq. SU7-0001 6.5 14.2.10.1 9 (12) Status board maintained during core load SU7-0001 5.7 14.2.10.1 9 (13) init nue of 8 assy,1 source v keff <0.95 SU7-S009 4.4 14 2.10.1 9 (14) Each assy. accom. by CR & ICRR monitor SU7-0001 4.10 14 2.10.1 9 (15) Final configuration Keff (0.95. SU7-S009 4.4 i

I u .

- - - - - - - --- - 1

KG&E PeSe 3

  • FSAR TEXT 01/09/85 Document PO TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 14.2.10 2 10 (a) RV press test, Yenting. STS PE-40 14.2.10.2 10 (b) CRDM mechanical, electrical & DRPI tests SU7-SF04 All 3 14.2.10.2 10 (c) Rx manual trip circuits checked. SU7-SF03.X 6.0 X=1-4 14.2.10 2 10 (C)1 Rod drop times measured. SU7-SF032 All 3 14.2.10.2 10 (C)2 Boron per Tech Spec's during RCC A tests. SU7-SF03.2 5.5 3 14.2.10.2 10 (e)3 SR monitored during RCC A tests. SU7-SF032 4.4 3 142.102 10 (d) Rx control / protect trip signals checked. SU7-SF05 All 3 l 14.2.10.2 10 (e) Func. check of flux mapping at NOT, NOP SU7-SRO1 All 3 14.2.10 2 11 (1) Crit.thru Rod withdrawal & boron dilut. SU7-0004 All -

14.2.102 11 (2) Conditions, precautions spec. by proc. SU7-0003 All 3 14.2.10 2 11 (3) Initially Contro1 Rod withdrawn. SU7-S011 6.3.11 14 2.10.2 11 (4) Boron diluted to achieve criticality. SU7-S011 4.8 14.2.10 2 11 (5) Monitor boron concentration during crit. SU7-S011 4.8 14.2.102 11 (6) ICRR plotted as func of RP & Boron cono. SU7-0002 All 14 2.10.3 11 Tl Lov Power Testing 142.10.3 11 (1)a Rx physies meas. after init. crit. SU7-0005 All 14.2.10.3 11 (1)b Verify static / kinetic characteristics. SU7-0005 All 142.10.3 11 (2) Proc. specify sequence & measurements. ADM01-070 52.2 3 142.10.3 11 (3) Plant in Safe Cond.-if test res. deviate ADM 01-070 5.3 14 2.10.3 11 (4) Rod Yorth Measurements SU7-SF09 All 3 14 2.10.3 11 (5) Isothermal temperature coefficient. SU7-000 All 142.10.3 11 (6) Boron concentration vorth SU7-0006 All 142.10.3 11 (7) Relative power distribution SU7-SR01 12 3 14.2.10.3 11 (8) Concurrent instrumentation tests. SU7-SE01 All 3 14 2.10.3 12 (1) Radiation surYegs performed. SU7-0016 All

KO&E P&ge 4 FSAR TEXT 01/09/85 Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 14.2.10.3 12 (2) RCS chemical sampling. SU7-SJ01 All 142.10.4 12 Tl Power Level Ascension.

142.10.4 12 (1) Hold points provided to evaluate results SU7-S008 92 14.2.10.4 12 (2) Min. tests specified by procedures. SU7-S008 6.0 14.2.10.4 12 (3) Relative power dist fn of power level SU7-SR01 A11 3 14.2.10.4 12 (4) Secondary heat balance cross-cal. SU7-SE02.4 6.6 3 14.2.10.4 12 (5) Ability of RCS to respond to instr. SU7-SF05 ALL 3 14.2.10.4 12 (6) Prwnary / secondary dgnamic response. SU7-0009 ALL 3 14.2.10.4 12 (7) System response char. meas. SU7-0010 ALL 3 14 2.10.4 12 (8) Rad-shield adequacy verified. SU7-0016 ALL l 14.2.10.4 12 (9) RCS Chemical sampling. SU7-SJ01 ALL 14 2.11 12 Test Program Schedule SU7-S008 ATT.

14.2.11 12 (1) Detailed schedules prepared. SU7-S000 42.4 14 2.11 12 (2) Docum. review of pre-op tests performed. SU7-S008 5.1.1 l

14.2.11 12 (3) S/U proc avai160 dags before fuel load. - -- ----

7 14 2.3 3 (1)' Test reviews 60 days before fuel load. 7 14.2.3 3 (2) Controls & methods described by adm proc ADM01-070 All 14.2.3.1 3 (1) Format & content per RO 1.68. ADM 07-100 101 14.2.3.1 5 (2) Sections signoff's, initia1 control proc ADM01-070 5.4.3 14.2.3.1 5 (3) Procedures prepared v/ latest design. -------- --

7 l

14.2.3.1 5 (4) Procedures reviewed by design org. ADM07-100 5.1.1.1 14 2.3.1 5 (5) Change based on approved design changes. - - -

7 14.2.3.2 5 1 Prec tech. reviewed by utility personnel. ADM 07-100 5.1.1.1 14 2.3.2 5 1(a) Reviewed for accuracg&technica1 content. ADM 07-100 5.1.1.1 14.2.3 2 5 1(b) Ensure design changes incorporated. 3,25

KG&E Pege 5

'* o' FSAR TEXT 01/09/85 Document PO TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 142.32 5 1(c) Proo. compatable v/ field installation. 3,25 142.32 5 1(d) Conformance to FSAR & Tech. Specs. ADM01-002 3.1 14.2.3 2 5 1(e) Review similar oper & test experiences. 7 14.2.3 2 6 (2) Committee performs final review. ADM07-100 42 3 14.2.0 6 Use of Rx operating & testing experience ADM-01-031 14.2.9 7 (1) Plant operating procedures. N/A 14.2.9 7 (2) Surveillance test demonstration. ADM 02-300 All 15.0 CHAPTER 15 15.0.6 10 instrument time delays TECH SPECS 3.3.1 3 3.0 CHAPTER 3 3.1.6 29 ECCS testing SU3-EMOX 3.9(B).2.1 5 Turbine stop valve instr during trip SU7-0015 6.4 3.9(B).2.1 - 6 Thermal expansion test SU7-0015 6.0 3.9(N).4.4 62 CRDM trip time SU7-SF03.X 6.0 X=1-4 4.0 CHAPTER 4 4.2.2.3.3 18 Four source assemblies SU7-0001 6.0 4.2.4.3 39 CRDM testing (see Reg Ouide 1.68) SU7-SFOX 6.0 X=1-4 4.4.5.3 45 LPMS calibration SU9-SQO2 6.0 CHAPTER 6 6.3.42.1 32 Si check valve tested before startup STS EP-205 7.0 CHAPTER 7 72222 OB Full flow ref established during ir.i S/U SU7-BB03 6.12.1 722.32 32 (1) Accuracy of RTD's demonstrated SU7-BB%.1 6.0 72.2.3.2 32 (2) Linearity of delta T measurements chk'd SU7-SF06 6.0 72.2.3.2 32 (3) RTD signals ccmpared with core exit T/C SU7-BB06.1 6.0

KO&E Pega 6 FSAR TEXT 01/09/85 TM mm PROCEDURE SECTION(S) NOTE 0.0 CHAPTER 8 8.3.1.1.2 7 Thermal overload relays t9 passed on MOVs y 9.0 CHAPTER 9 9.3.1.4 6 (1) ESF comporwnts tested for fail-safe oper 33 9.5.9.4 3 (1) Testing of the Aux Steam prior to S/U SU3-ALOX x=2,5 i

l l

i l

1 1

1

- - ._- - - - _ . . ~ - __- -- - - - . , -

. . , , KG&E Page 1 CHAPTER 14 TEST ABSTRACTS 01/09/85 Document PG TYPE COMMITMENT PR{EDURE SECTION(S) NOTE 14 2.12.3.1 153 Tl INITIAL CORE LO ADING SU7-0001 -

14.2.12.3.1.l a 153 OB Load fuel SU7-0001 6.0 14.2.123.1.1b 153 OB Measure Boron concentration SU7-0001 6.1.3.1 14.2.12.3.12a 153 PR Sufficient preop testing completed SU7-0001 5.16.1

- 14.2.12.3.1.2b 153 PRI STS are completed ADM 02-300 14.2.12.3.1.2b 153 PR2 Necessary systems are operable SU7-0001 5.16.1 142.123.1.3 153 TM Step by step core load sequence SU7-0001 62 14.2.12.3.1.4 153 AC2 Boron concentration is as specified SU7-0001 6.1.3.1 14.2.12.3.1.4 153 AC1 Permanent record of as loaded core SU7-0001 9.2.1 14.2.12.32 154 Tl Inv Count Rate Ratio for core load. SU7-0002 14.2.12.32.l a 154 08 Obt nuo monitor data dur init core load SU7-0002 6.0 142.12.3.2.1 b 154 OB Prevent criticality during core loading SU7-0002 1.3 142.12.3.2.2a .54 PR Temp & Plant SRNI op min 4 hrs for op. SU7-0002 U 142.12.322b 154 PR Plant ready for initial core load SU7-0001 5.0 14.2.12323 154 TM1 Monitor NIdata to access safety. SU7-0002 4.0 142.12.32.3 154 TM2 Inv count eval to prey dev from suborit SU7-0002 6.5.2 142.12.3.2.3 154 TM3 Core kept in suberit config dur coreload SU7-0002 4.5 14.2.12.3.2.4 154 AC Load core v/o achieving criticality. SU7-0002 9.1.1 14.2.1233 155 Tl Inv CRR mon for init criticality SU7-S011 63

.14 2.12.3.3.l a 155 OB Obt nuo mon data dur init criticality SU7-S011 6.3 14 2.12.3.3.1 b 155 08 Anticipate & determine criticality SU7-S011 6.3 14.2.12.3.32a 155 PR SR&lR alarm, trip, indication checked SU7-S011 5.9

~

14.2.12332b 155 PR Sl&lR nuo ch energized min 4 hrs for op SU7-S011 5.9 142.12.333a 155 TM1 Ob BLC prior to rod w/drav & boron dil SU7-S011 6.3.7

KG&E Pege 2 CHAPTER 14 TEST ABSTRACTS 01/09/65 Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 14.2.12.33.3a 155 TM2 After v/ draw &dur boron dil CR ob&lCRR ch SU7-S011 6.3.9.1 14.2.12.3.3.3b 155 TM Core react monit dur approach to critica SU7-S011 6.3.19 142.12.3.3.4 155 AC To determine criticality SU7-S011 9.3 142.12.3.4 156 Tl Initia1 Criticality (S-070004) SU7-S011 6.3 14.2.12.3.4.1 156 OB Achieve initia1 criticality SU7-S011 1.1 14 2.12.3.4.2a 156 PR initial core load completed SU7-S011 5.1 142.12.3.42b 156 PR Req STS completed & necessary systems op ADM 02-300 14.2.123.42c 156 PR Post-core load precritical test complete 51J7-S011 52 14.2.123.4.3a 156 TM Dur rod v/ draw & boron dil, data &lCR taken SU7-S011 6.3 14.2.12.3.4.3b 156 TM Int crit by boron dil or w/ draw of rods SU7-8011 6.3 14.2.12.3.4.4 156 AC Flux ley est @ 1x10-8 amps on IR nuo ch SU7-S011 9.3 142.123.5 157 Tl Determination of CPR for Physics Test SU7-S011 ---

14.2.12.3.5.1 157 081 Determine reactor power level SU7-S011 6.4 14.2.12.3.5.1 157 082 Establish range of neutron flux SU7-S011 6.4 142.12.3.52a 157 PR . Reactor critical & stable in IR SU7-S011 6.42,4 14.2.123.52b 157 PR Control rods sufficiently deep in core SU7-S011 6.4.6 142.12.3.5.2c 157 PR Reactor coolant temperature established SU7-S011 6.4.4,3 14.2.12.3.5.3a 157 TM1 Ytthdraw control rod bank SU7-S011 6.4.16 142.12.3.5.3a 157 TM2 Allow neutron flux level to increase SU7-S011 6.4.17 142.123.53b 157 TM Record RCPFL & IR channelcurrents SU7-S011 6.4.18 l

14.2.12.3.5.4 157 AC Power level for zero power test determin SU7-S011 6.4.20 142.12.3.6 158 TI ~ Boron Endpoint Determination (S-07006) SU7-S011 6.6 14.2.12 3.6.1 158 OB Determine crit react cool sys boron conc SU7-S011 5.17 142.123.6.2a 158 PR Reactor crit w/in range for zero test SU7-S011 6.6.2 14.2.12.3.62b 158 PR Reactor coolant @ normal op press & temp SU7-S011 6.6.3,4

. , . . , . KG&E Page 3 CHAPTER 14 TEST ABSTRACTS 01/09/85 Document P0 TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 142.12.3.62o 150 PR Rods @ approx end point configuration SU7-S011 6.6.1 14 2.12.3.6.3 158 TM Boron endpoints measured SU7-S011 6.6.18 14.2.123.6.4 158 AC Result of bor endp calc meet req of NDR SU7-S011 9.2.2 142.123.7 159 Tl isothermal Temp Coefficient Measurement SU7-S011 - - - - -

142.123.7.1 159 OB1 Determine isothermal temp coefficient SU7-S011 6.6 i 14.2.12.3.7.1 159 082 Derive mod temp coeff from isotherm data SU7-S011 1.2 142.1:c.";.72a 159 PR React crit w/in ra for zero power test SU7-S011 6.6.21 142.123.7.2b 159 PR RCS norm op press & temp. SU7-S011 6.63,4 142.12.3.72c 159 PR Cont rods @ approx end point config SU7-S011 6.6.14.1 14 2.12.3.7.3 159 TM1 IT temp coeff det by heat / cool RCS SU7-S011 6.627 3 14.2.123.7.3 159 TM2 Mod temp coeff derived from isoth data SU7-S011 6.631 142.123.7.4 159 AC Average ofisoth & mod temp coeff SU7-S011 7.10 14.2.123.8 160 Tl Power coefficient determination SU7-0008.X X = 1 to 4 14 2.12.3.8.1 160 08 Verify power coefficient of reactivity SU7-0008.X 1.1 14.2.123.8.2a 160 PR1 RCS press - nomina 12235 psig GEN 00-004 14.2.123.8.2a 160 PR2 RCC A,RCC bnk config - rods out, D @ bite SU7-S013 63.13 14.2.12.3.8.2a 160 PR3 RPL-30,50,75 & 90% RTP SU7-0008.X 5.2 142.123.82a 160 PR4 Tayg-const v/ nom val corres to Tayy prog SU7-0008.X 5.6 142.123.8.2b 160 PRI All subsys affectng PTR in auto mode op GEN 00-004 142.123.82b 160 PR2 CVCS demineralizer bypassed SU7-0008.X 53 14.2.12.3.8.3a 160 TM1 Oen eleo load changed SU7-0008.X 6.6 14 2.12.3.8.3a 160 TM2 Pri free responds y/out cont rod motion SU7-0008.X 6.6.4 142.123.8.3b 160 TM1 PCW cale by meas change in RCS temp /pwr SU7-0008.X 6.7.9 142.123.8.4 160 AC Val W agree v/dp ofisoth temp coeff SU7-0008.X 92.1 14.2.123.9 161 Ti Load Swing Tests (S-07009) SU7-S009.X X = 1 to 2

' ' , " KG&E Page 4 CHAPTER 14 TEST ABSTRACTS 01/09/85 Document P0 TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 14.2.12.3.9.1 161 OB Yerify nuo p1 transient response SU7-S009.X 1.1 142.12.3.92 161 PR SLC init from sse @ 30 ,75-&l00% power SU7-S009.X 5.2 14.2.12.3.9.3a 161 TM Manuai reduce turbine generator output SU7-S009.X 6.7 142.12.3.9.3b 161 TM P1 variables record v/ val on plinstru SU7-S009.X 6.9 14 2.12.3.9.4a 161 AC Reactor and turbine must not trip. SU7-S009.X 9.3.1 14.2.12.3.9.4b 161 AC Safety injection is not initiated. SU7-0009.1 9.3.2 3 142.12.3.9.4c 161 AC SG relief and safety valves do not lift. SU7-0009.1 9.3.3 3 14 2.12.3.9.4d 161 AC PZR relief and safety valves do not lift SU7-0009.1 9.3.4 3 14.2.12.3.9.4e 161 AC No manual contro1 req. for steady state. SU7-0009.1 9.3 3 142.12.3.9.4f 161 AC Nuclear power overshoot less than 3% SU7-0009.1 9.3.6 3 14.2.12.3.10 162 Tl Large Load Reduction Test SU7-0010.X X = 1,2 14.2.12.3.10.1 162 OB Show response to load changes. SU7-0010.X 1.1 14.2.12.3.10.1 162 002 Monitor control systems SU7-0010.X 1.2 14 2.12.3.10.1 162 083 Optimize control sys setpoints. SU7-0010.X 12 14 2.12.3.102 162 PR Load red. of 50% init. at 75 & 100% pyr. SU7-0010.X 6.0 14.2.12.3.10.3a 162 TM Reduce manually TG for 50% load reduc. SU7-0010.X 6.7 14.2.12.3.10.3b 162 TM Monitor & record plant variables. SU7-0011 142.12.3.10.3c 162 TM Adjust setpoints for optima 1 response. SU7-0010.X 4.3 14.2.12.3.10.4a 162 AC Reactor and turbine must not trip SU7-0010.X 92.1 14.2.12.3.10.4b 162 AC Safety injection is not initiated. SU7-0010.X 9.22 14.2.12.3.10.4c 162 AC Steam gen. safety valves do not lift. SU7-0010.X 92.4 142.12.3.10.4d 162 AC PZR safety valves do not lift SU7-0010.X 92.3 14.2.12.3.10.4e 162 AC No manual contro1 required SU7-0010.X 92 l

14 2.12.3.11 163 Tl Plant Trip from 100% Pyr. SU7-0011 14.2.12.3.11.1 163 0B1 Show auto con sys able to trip at 100% SU7-S011 1.1

r

. KG&E Page5 CHAPTER 14 TEST ABSTRACTS 01/09/85 Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 14.2.12.3.11.1 163 0B2 Determine response time of temp. det. SU7-S011 1.2 142.12.3.11.1 163 083 Evaluate data from trip SU7-0011 1.3 14.2.12.3.112a 163 PR RCS, SGL, P2R P&L, &SDS are in auto mode SU7-0011 5.6 142.123.11.2b 163 PR Plant operating at full power. SU7-0011 55 14.2.12.3.11.2o 163 PR Diesel generators standby idling cond. SU7-0011 5.9 14.2.12.3.11.3a 163 TM Initiate .y plant trip SU7-0011 6.8 14.2.12.3.11.3b 163 TM Adj.setpoints for optima 1 response SU7-0011 24 14.2.12 3.11.4 163 AC System within spec. limitations SU7-0011 9.0 14 2.12.3.12 164 Tl Rods Drop and Plant Trip SU7-0012 14.2.12.3.12.1 164 081 Show neg. RT circuit can trip reactor SU7-0012 1.1 142.123.12.2a 164 PRI RCS, SGL, PZR P&L, &FY pump in auto mode SU7-0012 5.1 142.123.122a 164 PR2 Steam dump system in T av mode. SU7-0012 5.1.4 142.12.3.122b 164 PR Plant operating at 30 to 5095 Pyr. SU7-0012 52 142.12.3.122c 164 PR Rod group & rods to be dropped are ID'd SU7-0012 5.5 14 2.12.3.12.3 164 TM Drop two Reca's from common group by NIS SU7-0012 6.10 142.123.122b 164 ' TM Monitor sys. prior to trip from 100% SU7-0012 6.9 14.2.12.3.12.4a 164 AC Reactor trip due to neg. rate trip. SU7-0012 9.1.1 14.2.12.3.12.4b 164 AC RCC A's release & bottom after trip signal SU7-0012 9.1.2 14.2.12.3.12.4c 164 AC PZR safety ValYes do not lift SU7-0012 9.1.3 14.2.123.12.4d 164 AC Steam Gen. safety valves do not lift SU7-0012 9.1.4 14.2.123.12.4e 164 AC Safety injection is not initiated. SU7-0012 9.1.5 14.2.12.3.13 165 Tl Automatic Steam Oen. Level Control SU7-AB01.X X = 1 to 6 14.2.12.3.13.l a 165 081 Verify stability of automatic SGLC. F J7- AB01.2 1.2 142.123.13.t a 165 082 Verify proper operation of FV pumps. SU7- AB01.3 1.2 142.123.13.I b 165 OB Show performance of SG Feedvater pumps SU7-AB013 1.2

,, , KG&E Page 6 CHAPTER 14 TEST ABSTRACTS 01/09/85 Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 142.123.132a 165 PR SGLC system checked and calibrated. SU7- AB01.1 5.1 142.12.3.13.2b 165 PR SGL instr. & setpoints set & calibrated. SU7- AB01.1 53 14.2.12.3.13.3a 165 TM Induce SGL trans. to prove SOLC response SU7- AB01.1 6.1 3 14.2.123.13.3b 165 TM1 verify variable speed features of SG FVP SU7-AB01.5 6.42 14.2.12.3.13.3b 165 TM2 verify performance char. of SG FV pumps SU7-AB014 6.5 14.2.12.3.13.4a 165 AC Auto SGL CS resp. same as Tech manual. SU7-AB01.X 9.0 142.12.3.13.4b 165 AC SG FYP perf. char. agree v/ design specs. SU7-AB01.4 9.2.1 14 2.123.14 166 Tl Dynamic Automatic Steam Dump Control SU7-AB02 ---

142.12.3.14.1 166 001 Prove operation of Tay steam dump ontr1. SU7-AB02 1.1 14.2.12.3.14.1 166 OB2 Show controller setpoint adequacy SU7-AB02 12 14.2.12.3.14.1 166 003 Get final settings for steam pzr control SU7-AB02 1.3 14.2.12.3.142a 166 PR RCS at normal psr & temperature. SU7-AB02 52 14.2.12.3.142b 166 PR Reactor is critical. SU7-AB02 52 14.2.12.3.142c 166 PR Steam dump system checked & calibrated SU7-AB02 5.4 14.2.12.3.14.2d 166 PR Main FY and condensor are operational. SU7-AB02 5.9,5.12

~

142.12.3.143a 166 TM Reactor power increased. SU7-AB02 6.4.6 142.12.3.14.3b 166 TM Psr. controller setpoint increased. SU7-AB02 6.4 142.12.3.14.3c 166 TM1 . Simulate turbine trip . SU7-AB02 6.5 142.12.3.14.3c 166 TM2 Open sieam dump valves SU7-AB02 6.5 14 2.12 3.14.4 166 AC Steam dump sys sustain stble reac. T av SU7-AB02 9.2 14.2.12.3.15 167 Tl RTD Bypass Flow Measurement SU7-BB01 14 2.12.3.15- 167 0B1 Measure flow rate for design trans. time SU7-BB01 1.1 14.2.12.3.15.1 167 082 Measure Flow Rt. in each RTD bypass loop SU7-BB01 1.1 14 2.123.1524 167 PR Component testing & calibration complete SU7-BB01 5.1 142.12.3.152b 167 PR Power supplies circuits operational SU7-BB01 52,5.3 L  ;

.. ., KG&E Page7 CHAPTER 14 TEST ABSTRACTS 01/09/85 Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 14.2.123.15.2c 167 PR1 Reactor core is installed. SU7-BB01 5.5 14.2.12.3.15.2c 167 PR2 Plant at normal temperature & P2R SU7-BB01 5.5 14 2.12.3.15.3 167 TM1 Flow rate calculated SU7-BB01 6.1.2 14.2.123.153 167 TM2 Hot & cold RTD flow data recorded. -

SU7-BB01 62 l

l 14.2.12.3.15.4 167 AC - Flow rate within design specifications SU7-BB01 92 14.2.12.3.16 168 Tl PZR Heater and Spray Capability Test SU7-BB02 -----

14.2.12.3.16.1 168 081 Determine rate of pzr reduction SU7-BB02 1.t a 14.2.12.3.16 .1 168 082 Determine rate of pressure increase SU7-BB02 1.1b 14 2.12.3.16 .2a 160 PR Component testing & calibration complete SU7-BB02 5.1 14.2.12.3.16 .2b 168 PR Electrical power & circuits operational SU7-BB02 5.3 14.2.12.3.16 .2c 168 PR Core installed, plant in hot shutdown. SU7-BB02 56 14.2.12.3.16 2d 168 PR - Setting of continuous spray complete SU7-BB02 5.5 142.12.3.16 2e 168 PR Reactor Core Sgstem Borated. SU7-BB02 5.9 142.12.3.16 2f 168 PR Test performed prior to init crit. SU7-S010 5.6/6.3.1 142.12.3.16 .3a 168 TM1 Sprag va1Yes closed. SU7-BB02 6.1 14.2.12.3.163a 168 TM2 Time to reach 2,300 psig is meas./ree. SU7-BB02 6.1 142.12.3.163b 168 TM1 Pressurizer heaters deenergized. SU7-BB02 6.1 14.2.12.3.16.3b . 168 TM2 Time to reach 2,000 psig is meas. & rec. SU7-BB02 6.1

, 14.2.12.3.16.4 168 ACI PZR sprag response equals design limits. SU7-BB02 9.2.1 l

14.2.12.3.16.4 168 AC2 PZR hir response =to design limits. SU7-BB02 922 14.2.12.3.17 169 Tl Reactor Coolant Sgstem Flow Measurement SU7-BB03 14.2.12.3.17.l a 169 08 Confirm RCS flow rate + or =to 90%/DFR SU7-BB03 1.1 14.2.12.3.17.1 b 169 08 Confirm RCS flow is +or=to ther.dsgn. FR SU7-BB02 9.2.1 142.12.3.17.2a 169 PR Component testing calibration complete. SU7-BB03 5.1 12 14.2.12.3.172b 169 PR Electrical power circuits operational SU7-BB03 5.3

l KGM Pa0e 8 CHAPTER 14 TEST ABSTRACTS 01/09/85 i Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 14.2.12.3.172c 169 PR1 Reactor core is installed. SU7-BB03 5.6

' 142.12.3.17.2c 169 PR2 Plant at normal temp. & pressure. SU7-BB03 5.6 142.12.3.17.3a 169 TM Before critical operation, RCS FR calc. SU7-BB03 6.1 14.2.123.173b 169 TM During init. pyr. oper. RCS FR calc. SU7-SCO3 6.0 14.2.12.3.17.4 169 AC RCS flow rate + or =to 90% of ',es. value SU7-BB03 9.2.1 14.2.12.3.18 170 Tl RCS Flow Coastdon Test SU7-BB04 14.2.12.3.18.1 a 170 08 Measure rate RCS changes after pump trip SU7-8804 1.1 14 2.133.18.1 b 170 OB Deter. low-flow delay - or =to saf. anal SU7-BB04 9.1.2 142.12.3.182a 170 PR Component testing & calibration complete SU7-BB04 5.1 12 142.12.3.182b 170 PR Power supplies & circuits operational SU7-BB04 53 142.12.3.18.2c 170 PR1 Reactor core is installed SU7-BB04 5.7 14.2.123.182c 170 PR2 Plant at normal temperature & pressure. SU7-BB04 5.7 14 2.12.3.103 170 TM Coastdown & delay time data recorded. SU7-BB04 62 142.123.18.4a 170 AC Change rate RC flow within design specs. SU7-BB04 9.1.1 14.2.12'.3.18.4b 170 AC RCS low-flow times - or =to safety anal. SU7-BB04 9.1.2 14 2.123.19 171 Tl PZR continuous Spray Flow Verification. SU7-BB05 14 2.12.3.19.1 171 OB Establish setting for pzr spray flow SU7-BB05 1.0a 142.12.3.192a 171 PR Component testing calibration vomplete. SU7-BB05 5.1 12 ,

14.2.12.3.192b 171 PR Power supplies and circuits operational SU7-BB05 5.3 142.123.192c 171 PRI Reactor core is installed. SU7-BB05 5.4 14.2.123.19.2c 171 PR2 Plant at normal temperature SU7-BB05 5.4 142.12.3.192d 171 PR Reactor coolant system is borated. SU7-BB05 5.7 142.12.3.19.2e - 171 PR Test performed prior to init, crit. SU7-S016 5.4,63.1 142.12.3.192f 171 FR Prelim setting of SF complete during HFT SU3-BB05 25 14 2.12.3.193 171 TM1 Spray flow valves adj. to optimum flow. SU7-BB05 6.1

I KG&E Page 9 CHAPTER 14 TEST ABSTRACTS 01/09/8S Document PG TYPE COMMITMENT PROCEDURE CECTION(S) hDTE 14 2.12.3.19.3 171 TM2 Va1Ye throttle positions are recorded. SU7-BB05 6.1 14.2.123.19.4 171 AC SF YalYes throttled to keep line warm SU7-BB05 9.3 14 2.12.3.20 172 Tl RTD/TC Cross Calibration SU7-BB06.X X = 1,2 14.2.12.320.l a 172 081 Provide checkout of RTD's & incore ther. SU7-BB06.1 6.0 14.2.12.320.l a 172 082 Generate isotherrmal cross-calib. data. SU7-BB06.1 6.6.4 142.12.3.20.1 b 172 OB ProYide a func. checkout of the TCCM SU7-BB06.2 1.1 14.2.12.3202a 172 PR Component testing & calibration complete SU7-BB06.1 52 12 14 2.123202b ~ 172 PR Power supplies & circuits operational. SU7-S010 B 14.2.12.3.20.2o 172 PR Plant heatup is in progress. SU7-S010 622 14.2.12.3.20.3a 172 TM1 At Yarious temp plateau data is recorded SU7-BB06.1 142.12.3.20.3a 172 TM2 Cross-calibration determined. SU7-BB06.1 7.B 142.123203b 172 TM1 TC core subcooling monitor operational. SU7-BB06.2 6.1 142.12.3.20.3b 172 TM2 Programmable functions are verified. SU7-BB%.2 6.1 - 6.6 142.12.320.4a 172 AC Indy. RTD readings within design specs. SU7-BB06.1 92.1 142.12.320.4b 172 AC Corrections of RTD's within design specs SU7-BB06.1 9.2.1 142.123.20.4c 172 AC TCCM in accordance with design specs. SU7-BB06.2 9.2.1,2 14 2.12.3.21 173 TI CL Instrumentation & NS Requirements SU7-SC01 142.12.321.1 173 081 Verify instr. prior to fuel-loading. SU7-SC01 1.1 14 2.12.3.21.1 173 082 Check neutron resp. of NIS source range. SU7-SC01 12 142.12321.1 173 083 Check neutron response after Bhr delay. SU7-SC01 13 142.12321.1 173 004 Verify S/N ratio ) 2. SU7-SC01 1.4 14.2.12.321.2a 173 PR Hot functional testing is completed. SU7-SC01 26 142.12.3.212b 173 PRI Nuclear instr. sys. is installed. SU7-SC01 5.4 142.123.212b 173 - PR2 Nuclear instr. sys. is calibrated. SU7-SC01 5.4 14.2.12.3.21.3a 17; TM Verify align.of temp. Instr.v-port.NS SU7-SC01 6.1,6.2

.. . 'KG&E Page 10 CHAPTER 14 TEST ABSTRACTS 01/09/85

{

Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 142.12.321.3b 173 TM Port. NS to check NR of NIS source range SU7-SC01 62 142.12.3.21.3c 173 TM1 Verify temp. SR after 8 hr delay. SU7-SC01 6.3 142.12.321.3c 173 TM2 Verify temp. NIS source range after 8 hrs SU7-SC01 6.3 142.12.321.3d 173 TM Perform statistical evaluation. SU7-SC01- 63.3.1 142.12.321.4 173 AC2 S/N Ratio > 2 SU7-SC01 9.5 14 2.12.3.21.4 173 ACI Neutron instrumentation operational. SU7-SC01 9.4 14 2.12.3.22 174 Tl Thermal Pwr. Meas. & SP Data Collection SU7SCO3.XX XX = 1to 8 142.12.322.1 174 081 Measure core thermal power. SU7-SC03.X 6.0 14.2.12.3.22.1 174 082 Obtain data for instr. & calibration. SU7-SC03.X 6.0 142.12.3222a 174 PR Deleted SU7-SC03.X 142.12.322.2b 174 PR Calorimetric instr. is installed. SU7-SC03.1 6.0 14.2.12.3.222c 174 PR Test is performed at 30,50,75,90 & 100%. SU7-SCO3.2 5.1 3 142.12.322.3 174 TM1 Collect data & calculate thermal pvr. SU7-SCO3.X 6.4 3 14.2.12.322.3 174 TM2 Obtain statepoint data. SU7-SC03.X 6.3 3 14 2.12.3.22.3 174 TM3 Compute agYerage for each parameter. SU7-SCO3.X 6.4 3 14 2.12.3.22.3 174 TM4 Convert to appropriate units. SU7-SCO3.X 6.4 3 14.2.12.322.3 174 TM5 Summarize data for each RCS loop. SU7-SC03.X X = 1 to 8 3 14.2.12.322.3 174 AC This test is for the collection of data. SU7-SCO3.X 92.1 3 14.2.12.323 175 Tl Operational Alignment of NI. SU7SE02.XX XX=1 to 10 142.12.323.1 175 081 Establish settings on SR instr. SU7-SE02.1 1.1 3 142.12.323.1 175 OB2 Establish settings on ISR instr. SU7-SE02.2 1.1 3 14 2.12.3.23.1 175 083 Establish settings on PR instr. SU7-SE02.2 1.1 3 142.12.3232a 175 PR Nuclear instrumentation sys. aligned. SU7-SE02.1 52 3 142.12.3232b 175 PR3 Test vill be conducted at 100% pyr. SU7-S0XX X=11 to 16 142.12.3232b 175 PRI Test will be conducted prior to crit. SU7-S010 6.3.11

T

.e ., KG&E Page 11 CHAPTER 14 TEST ABSTRACTS 01/09/85 Document P0 TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 142.12.3232b 175 PR2 Test will be conducted during pvr. aso. SU7-S015 6.0 14 2.12.3.23.3 175 TM Functions calibrated, tested, & verified. SU7-SE02.2 6.0 3 142.12.323.3b 175 TM Operational modes set per test instrue. SU7-SE02.4 6.0 3 14.2.12.323.4 175 AC1 Overlap must be at least 1 1/2 decades. SU7-SE02.4 9.2.1 3 142.12.3.23.4 175 AC2 Pyr. range channels agree with PCC. SU7-SE02.4 922 3 14.2.12.324 176 Tl Axial Flux Difference instr. Calibration SU7-SE03.X X = 1 to 3 14.2.12.324.1 176 03 Derive calibration factors. SU7-SE03.X 6.0 X=1-2 14.2.12324.2a 176 PR Axial flux differ, inst has been aligned SU7-SE032 5.1 14.2.12.324.2b 176 PR Data obtained at 30% & 50% power. SU7-SE03.1 5.5 14 2.12.3.24.3 176 TM1 Collect data at 75% power. SU7-SE03.2 6.1 14 2.12.3.24.3 176 TM2 Perform delta l calculations. SU7-SE03.2 6.3 142.123243 176 TM3 Extrapolate results for use at 100% pyr. SU7-SE03.2 6.12 142.12.324.4 176 AC Calibration factor agree with tech specs SU7-SE03.2 9.6 14.2.12.325 177 TI CRD Mechanism Operational Test SU7-SF01.4 14.2.12.3.25.1 177 081 Show operation of the Rod Drive Mech. SU7-SF01.4 1.2 14.2.123 25.1 177 082 Provide proof of slave cycler timing. SU7-SF01.4 1.1 142.12.325.2a 177 PR CRDM's are installed. SU7-SF01.4 5.1 142.12.3252b 177 PR1 Rod drive motor-gen. sets are installed. SU7-SF01.4 5.9 142.12.3.25.2b 177 PR2 Power is available SU7-SF01.4 5.9 142.12.3252c 177 PRI Core is installed. SU7-SF01.4 5.1 14.2.12.3252c 177 PR2 DRPIis installed. SU7-SF01.4 5.1 14.2.12.325.2c 177 PR3 CRDM cooling fans are operational. SU7-SF01.4 5.7 14.2.12.3.252d 177 PR Nichannels are available. SU7-SF01.4 4.2

- 142.12.3252e 177 PR Fast speed oscillograph is available. SU7-SF01.4 6.1.3 14.2.12.325.34 177 TM1 Confirm signals to CRDM step. mag. coils SU7-SF01.4 6.1.8

. 4 KG&E Page 12 CHAPTER 14 TEST ABSTRACTS 01/09/85

- Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 14.2.12.325.3b 177 TM1 Yerify operation of CRDM's . SU7-?F01.4 6.1 142.12.325.3b 177 TM2 CRDM Magnet coi1 currents are recorded. SU7-SF01.4 6.1.3 14.2.12.325.3b 177 TM3 Audio noise signals are recorded. SU7-SF01.4 6.1.3 14.2.12.3.25.4 177 AC Control rods conform to requirements. SU7-SF01.4 9.2.1 142.12.3.26 178 Tl Rod ControlSystem SU7-SF02 14.2.12.326.1 178 OB Demonstrate RCS prior to init. crit. SU7-SF02 1.1 14.2.12.3.26.1 178 083 Show operation of rod inhibit functions. SU7-SF02 6.0 14.2.12.3.262a 178 PR1 RCS at normal operating pressure. SU7-SF02 5.1 142.12.326.2a 178 PR2 RCS at normal operating temperature. SU7-SF02 5.1 142.12.3.26.2b 178 PR Rod controlsys installed & aligned. SU7-SF02 52 142.12.3.262c 178 PR Source range nuc. instruments operable. SU7-SF02 5.3 14.2.12.326.2d 178 PR Rods are capable of withdrawal. SU7-SF02 6.0 142.12.3.262e 178 PR DRPI system is operable. SU7-SF02 5.12 14.2.12.326.3a 178 TM2 Control is checked prior to init. crit. SU7-SF02 6.0 142.12.3.26.3b 178 TM1 Status lights are verified. SU7-SF02 6.7.1 142.12.326.3b 178 TM2 Alarms are verified. SU7-SF02 6.0 14.2.12.3.26.35 178 TM3 Indicators are verified. SU7-SF02 6.8.3 142.12.326.4 178 AC1 Control functions agree v-RPIS & RCS man SU7-SF02 6.0 14.2.12.326.4 178 AC2 Indication function agree v-RPIS & RCS SU7-SF02 6.0 14.2.12.326.4 178 AC3 Restrict rod motion v/ inhibit function. SU7-SF02 6.0 142.12.327 179 Tl Rod Drop Time Measurement SU7-SF03.X X=1 to 4 14.2.12.327.1 179 082 Determine rod drop time under FF cold. SU7-SF03.2 1.1 14 2.12.3.27.1 179 081 Determine rod drop time under NF cold. SU7-SF03.1 1.1 SU7-SF03.4 1.f 14.2.12.327.1 -179 083 Determine rod drop time under NF hot.

14.2.12.327.1 179 OB4 Determine rod drop time under FF hot. SU7-SF03.3 f .1

... ., KG&E Page 13 CHAPTER 14 TEST ABSTRACTS 01/09/85 l Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 142.12.327.2a 179 PR initial core loading is completed. SU7-SF03.1 5.2 142.12.3272b 179 PR Rod control sys. is installed and tested SU7-SF03.1 5.3 14.2.12.3.27.2c 179 PR RPlis installed and checked. SU7-SF03.1 5.3 142.123273 179 TM1 Vithdrav each rod cluster control assy. SU7-SF03.1 6.5.1 14.2.12.327.3 179 TM2 Interrupt electrical power. SU7-SF03.1 6.5.4.1 14.2.12.327.3 179 TM3 Measure & record the rod drop (1 hie. SU7-SF03.1 6.5.4.5 14.2.12.3.27.3 179 TM4 Reactor at C & H conditions, & NF & FF. SU7-SF03.X 6.0

.14.2.123.27.4 179 AC Rod drop times agree with tech. specs. SU7-SF033 9.1.1 14 2.12.3.28 100 Tl Rod Position Indication System SU7-SF04.X X=1&2 14.2.12.3.28.1 180 0B1 RPl sys performs indication functions. SU7-SF04.X 1.1 142.12.328.1 180 083 Each rod operates over its entire range. SU7-SF04.X 1.2 14.2.123282a 180 PR1a Test at T < 200 F. SU7-SF04.1 5.1 142.12.3282a 100 PR2a Verify at T nom. 557 F. SU7-SF042 5.1 14.2.12.328.2b 180 PR At least. one reac. cool. pump in service SU7-SF04.2 5.1 27 14.2.12.328.3a 160 TM1 All shutdown rod banks fully withdrawn. SU7-SF04.X 6.6.1 142.12.3.283a 180 TM2 Record rod position. SU7-SF04.X 6.62 142.123283b 180 TM1 Contro1 rod banks fully withdrawn. SU7-SF04.X 6.7.1 14.2.123283b 180 TM2 Record rod position. SU7-SF04.X 6.7.2 14.2.12.3.283c 180 TM PA converter readout recorded. SU7-SF04.X 6.7.2.4 142.12328.4 180 Act RPI sys performs required alarm function SU7-SF04.X 92 14 2.12.3.28.4 180 AC2 Each rod operates over travel range. SU7-SF04.X 92.4 14 2.12.3.29 181 Tl Automatic Reactor Control System SU7-SF05 14.2.123 29.1 181 081 Show RC able to respond to input signals SU7-SF05 6.0 I

14.2.123 29.1 181 082 Show RC able to transmit signals. SU7-SF05 6.0 14.2.123292a 181 PR Reactor is at 30% power. SU7-SF05 5.2

,, ,, KG&E Page 14 CHAPTER 14 TEST ABSTRACTS 01/09/85 Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NCTE 14.2.12.3.292b 181 PRI PZR level & pressure systems in auto. SU7-SF05 5.3 14.2.12.3292b 181 PR2 Steam dump system in automatic. SU7-SF05 5.3.3 14.2.12.3292b 181 PR3 Steam generator level system in auto. SU7-SF05 5.3.4 14.2.12329.2b 181 PR4 Main feed pump speed control sys in auto SU7-SF05 53.5 142.12329.3 181 TM1 T ave varied from Iret selpoint. SU7-SF05 6.10 14 2.12.3.29.3 181 TM2 Verify recovery capabilities of auto RCS SU7-SF05 6.12 14.2.12.3.29.4a 181 ACI No manual contro1 required. SU7-SF05 9.2.1 14.2.123.29.4b 181 AC1 Tay return to + 1.5F after 6F transient. SU7-SF05 922 14.2.12.329.4o 181 AC Rod motion is irtibited. SU7-SF05 6.0 14 2.12.3.30 182 Tl Operational Align. of Proc. Temp. Instr. SU7-SF06.X X = 1 to 6 14.2.12.3.30.1 182 081 Align T and T PI prior to criticality SU7-SF06.1 1.1 14.2.123 30.1 182 082 Align T and T Proc. Instr. at power. SU7-SF062 1.1 3 14.2.12.3.302a 182 PR2 Alignment prior to init crit at 75% pyr. SU7-SF06.4 6.0 142.12.3.302a 182 PRI Alignment prior to init. crit. & at 75%. SU7-SF06.1 5.2 3 142.12.3.302a 182 PR3 Alignment will be checked at 100% pyr. SU7-SF06.6 6.0 182 PR All reactor coolant pumps operating. SU7-SF06.1 52 l .14.2.123302b 14.2.12.330.3a 182 TM1 Align T and T prior to crit & at 75%. SU7-SF06.1 6.1 3 14.2.12.3.30.34 182 TM2 Collect 75% data for T and T values. SU7-SF06.4 6.10 14.2.12.3.30.34 182 TM3 Use collected data (TM2) for 100% pyr. SU7-SF06.6 6.14,16 14.2.122302b 182 TM1 Align of T and T agree with TPM. SU7-SF06.6 6.0 14.2.12.3.30.3b 182 TM2 Realign channels as nec. per test specs. SU7-SF06.6 6.10,12 14 2.12.3.30.4 182 AC T and T channels must agree v/ design. SU7-SF06.6 6.4 14.2.12.3.31 183 Tl Startup Adjustments of RCS SU7-SF07.X X = 1 to 5 14 2.12.331.1 183 OB Obtain optimum plant efficiency. SU7-SF07.X 1.1 14.2.123.312a 183 PR RCS at normal psr. & temp. SU7-SF07.1 5.1

., KG&E Page 15 j CHAPTER 14 TEST ABSTRACTS 01/09/85 Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 14.2.12.3.31.2b 183 PR Align.per Oper Align of Proc Temp instr SU7-SF07.1 5.3 3 14.2.12.3.312c 183 PR Turbine control system is aligned. SU7-SF07.1 5.4 3 142.12.3.31.3a 183 TMM Obtain sys temp & steam psr. data. SU7-SF07.1 6.1 3 14.2.12.3.313b 183 TM Data vill provide basis for adj to RCS. 7J7-SF07.3 6.6 3 14.2.12.3.31.4 183 AC T controller maintain spec. steam psr. SU7-SF07.4 6.0 14 2.12.3.32 184 Tl RCCA or Bank Yorth Meas. at Zero Power SU7-S011 6.1 14.2.12.3.32.1 184 OB Determine worth of a RCC or RCCA. SU7-S011 6.6 142.12332.2a 184 PR Reactor is critical. SU7-S011 6.638 142.12.3.322b 184 PR RCS at normal operating psr. & temp. SU7-S011 6.6.39,40 14.2.12.3.32.3 184 TM1 RCC & RCCA validated by +or-of B in RCS. SU7-S011 6.6

-14 2.12.3.32.3 184 TM2 Cause rod movement . SU7-S011 6.6 142.123323 184 TM3 Rod movement causes reactivity change. SU7-S011 6.6 14.2.12.3.32.3 184 TM4 Changes are used to compute worths. SU7-S011 6.6 14 2.12.3.32.4 184 AC Yorth of RCC or RCCA agrees v NDR & VDD. SU7-S011 9.12 92.4 14 2.12.3.33 185 Tl RCCA or Bank Yorth Meas. at Power SU7-SF09.X X = 1 to 2 14.2.12.333.1 185 081 To measure RCCA for an ejected rod. SU7-SF09.1 6.0 142.12.3.33.1 185 OB2 Incore resp to dropped rod. SU7-SF09.2 6.0 14 2.12.3.33.2 185 PRI Testing performed at 3095 power. SU7-SF09.1 5.1 14.2.12.3.33.2 185 PR2 Testing performed at 50% power. SU7-SF092 5.1 142.123.333a 185 TM1 Ejected Rod. SU7-SF09.1 6.0 14.2.12.3.33.3b 185 TM2 Dropped rod. SU7-SF09.2 6.0 14.2.12.3.33.4a 185 AC Ejected Rod Yorth agrees v/ NDS SU7-SF09.1 9.0 142.12.3.33.4b 185 AC Dropped Rod Yorth agrees v/NDC. SU7-SF092 9.0 14.2.123 34 186 Tl Reactor Systems Sampling for Core Load SU7-SJ01 -----

14 2.12.3.34.1 186 08 Yerify boron in RCS & Auxiliary systems. SU7-SJ01 1.1 i 3

. KG&E Page 16 CHAPTER 14 TEST ABSTRACTS 01/09/85 Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 14 2.12 ',34.2a 186 PR1 Boric acid tank filled v/ boric acid. SU7-SJ01 5.1 142.12.3342b 186 PR RCS filled with RG vtr. per tech. specs. SU7-SJ01 5.6 142.12.3.34.3a 186 TM Fill & circulate the RCS v borated vtr. SU7-SJ01 5.6,6.3 142.12.3.343b 186 TM1 Collect & analyze 4 smp1. taken from RCS SU7-SJ01 6.4 142.12.3.34.3b 186 TM2 1 sample from oper. resid. heat rem. loop SU7-SJ01 6.4 14 2.12.3.34.4 186 AC Boron of samples within 30 ppm range. SU7-SJ01 9.4 14 2.12.3.35 187 ATTN: DELETED.

14.2.12.336 188 Tl SD & Maint. of Hot Standby Ext. to C R SU7-0014 142.12.3.36.1 188 OB1 Show plant can be taken from >10% to HS. SU7-0014 1.1 14 2.12.3.36.1 188 082 Verify plant can maintain HS for 30 MIN. SU7-0014 1.1 14.2.12.3.36.1 188 083 Use of controls & instr. ext. to C R SU7-0014 1.1 14.2.12336.2a 188 PR Component testing & calibration complete SU7-0014 8,12 142.12.3.362b 188 PR1 Electrical power supplies operational. SU7-0014 8 142.12.3.362b 188 PR2 Control circuits are operational. SU7-0014 8 142.12.3.362c 188 PR P' ating at >10 percent pyr. SU7-0014 5.3 14.2.12.3362d 188 PR Con. bs. auth. & resp. specified. f)7-0014 5.5,6 14.2.12.3.36.3a 188 TM Plant taken from >10% to hot standby. SU7-0014 6.3 14.2.12.3.36.3b 188 TM Maintain hot standby for 30 minutes. SU7-0014 6.10 142.12.336.3c 188 TM All actions by CR0 doc. within proc. SU7-0014 appx. C 142.12236.4 188 AC1 Plant can be taken from >10% to HS. SU7-0014 9.1.1 14 2.12.3.36.4 188 AC2 Condition maintained for 30 minutes. SU7-0014 9.1.1 14.2.12.3.36.4 188 AC3 Use of a plant procedure. SU7-0014 9.1.1 14 2.12.3.36.4 188 AC4 Minimum shift crew utilized. SU7-0014 9.1.1 14.2.12.3.36.4 188 AC5 Controls & instr. ext. to control room. SU7-0014 9.1.1 l

l 14 2.12.3.37 189 Tl Power Asc. Ther. Exp. & Dynamic Test. SU7-0015

., .. KG&E Pege 17 CHAPTER 14 TEST ABSTRACTS 01/09/85 Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 14 2.12.3.37.14 189 08 Show that sys. points respond per design SU7-0015 6.0 14.2.12.3.37.1 b 189 081 Show sys. piping exp. without obstr. SU7-0015 6. 0 14.2.12.3.37.1 b 189 082 Expansion in accordance with design. SU7-0015 1.0a 142.123.37.I b 189 083 Piping returns to cold pos. per design. SU7-0015 65 142.12.3.372a 189 PR Reference points are established. SU7-0015 6.1 142.12.3.37.2b 189 PR Pyr. asc. testing in progress. SU7-0015 6.0 142.12.3.37.2c 189 PR Subject systems avail. for spec. oper. SU7-S015 5.1 14.2.123372d 189 PR Instrument calibration is complete. SU7-0015 5.7 142.12.3.372e 189 PR Preservice insp. complete within 6 mos. SU7-0015 5.8 14.2.12.3.37.34 189 TM Record cold baseline data. SU7-0015 6.1 14.2.12.3.37.3b 189 TM Obtain measurement data. SU7-0015 62 142.123373c 189 TM Systems are aligned for operation. GEN SERES 14.2.12.337.3d 189 TM1 Pump operation & valve operation is init GEN SERIES 142.12.3.37.3d 189 TM2 Sgstem is monitored for response. SU7-0015 6.4.6 142.12.3.37.3e 189 TM Obtain measurement data after cooldown. SU7-0015 6.5 142.12.337.4a 189 AC 'No evidence of ulocking exc. per design. SU7-0015 92.1 142.12.3.37.4c 189 AC2 Snubber swing clearance satisfactorily. SU7-0015 922 142.12.3.37.4b 190 AC ToS1 stresses do not exceed code limits SU7-0015 9.2.4 142.12.3.37.4c 190 AC1 Spring hanger movement within H & C StPt SU7-0015 9.2.2 142.12337.4c 190 AC3 Snubbers do not fully retract or expand. SU7-0015 92.2 142.12.3.37.4d 190 AC piping return to baseline pos per desir . SU7-0015 92.3 14.2.12.3.37.4e 190 AC Movement within 25% of anal VI or T-25" SU7-0015 9.2.5 14.2.12.3.38 191 Tl Incore Flux Mapping SU7-SR02 -

3 14.2.123.38.1 191 08 Obtain core pyr. & temp. profiles. SU7-SR02 6.0 142.12.3.382a 191 PR Incore monitoring system has been tested SU7-SROX X=3,4

. KG&E Page 18 CHAPTER 14 TEST ABSTRACTS 0I/09/85 Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 14.2.12.3.382b 191 PR Test performed at low pvr,30,50,75,10095 SU7-SR02 6.0 142.12.338.2c 191 PR Reactor stabilized prior to taking a map SU7-SR02 6.0 14.2.12.3.38.3 191 TM1 Movable detectors inserted into core. SU7-SR02 6.1 14.2.123383 191 TM2 Data is obtained. SU7-SR02 6.1 14 2.12.3.38.3 191 TM3 Thermocouples monitored at stable pvr. SU7-SR02 6.1 14 2.12.3.38.3 191 TM4 Data is retained for evaluation. SU7-SR02 6.1 14.2.12.3.38.4 191 AC Flux & temperature data obtained . SU7-SR02 9.3 3 14.2.123 39 192 Tl Incore Instrumentation Test SU7-SR04 3 14.2.12.339.1 192 OB Set up & show operation of ino Instr Sys SU7-SR04 1.1 3 14.2.12.3.39.2a 192 PR Incore instsrumentation sys is installed INSTALLED 12/84 1 14.2.12.3.392b 192 PR Rotation & limit switch oper. verified. SU7-SR03 5.6 142.12.3392c 192 PR1 Testing perfr. med at cold shutdown. SU7-SR03 5.1 14.2.12.3.392o 192 .PR2 Testing performed at hot shutdown. SU7-SR04 5.1 14 2.12.3.39.3 192 TM1 At CS dummy cable ins. into each thimble SU7-SR03 6.4 14 2.12.3.39.3 192 TM2 At HS detectors inserted into thimbles. SU7-SR04 6.6 142.12339.4 192 AC Inc ins sys capable of taking a flux map SU7-SR04 92 3 142.12.3.40 193 Tl Biological Shield Testing SU7-0016 14.2.12.3.40.l a 193 08 Measure & record radiation levels. SU7-0016 12 142.12.3.40.1b 193 08 Determine where shielding is deficient. SU7-0016 1.3

. 142.123.40.1c . 193 08 Ensure personnel will not be overexposed SU7-0016 1.4 14.2.12.3.40.2a 193 PR instrument calibration complete. SU7-0016 5.6 14.2.12.3.40.2b 193 PR Reactor power levels attained. SU7-0016 5.5 14 2.12.3.40.3 193 TM Neutron & gamma ray surveys conducted. SU7-0016 6.1 14 2.123.40.4 193 AC1 Neutron & gamma rag surveys complete. SU7-0016 9.1 14 2.12.3.40.4 193 AC2 Implement admin controls per 10 CFR 20 SU7-0016 9.1 22

.n --

KG&E Page 19 CHAPTER 14 TEST ABSTRACTS 01/09/85 Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 14.2.123.41 194 Tl Natural Circulation Test SU7-0024 142.12.3.41.1 194 081 Show time required to stabilize nat cire SU7-0024 1.1 14 2.12.3.41.1 194 082 Show core flow distribution. SU7-0024 12 142.123.412a 194 PR Low power physics testing complete. SU7-0024 52 142.123.412b 194 FR instrumentation installed & calibrated. SU7-0024 5.0 142.12.3.41.2c 194 PR Plant operation at SS cond. at 3% power. SU7-0024 28 14 2.12.3.41.3 194 TM1 Reactor coolant pumps tripped at 3%. SU7-0024 6.5 142.123.413 194 TM2 Transients are monitored. SU7-0024 6.11 14.2.123.41.3 194 TM3 Estab. of natural circulation verified. SU7-0024 6.12 14.2.12.3.41.4 194 ACI Nat. circ. nas been demonstrated. SU7-0024 9.1.1 14.2.12.3.41.4 194 AC2 Meas. core T no >than RCS T per design SU7-0024 9.1.2 14.2.123.42 195 Tl Loss of Heater Drain Pump Test SU7-0017 14.2.12.3.42.1 195 OB Yerify response to loss of htr drn pump. SU7-0017 1.1 142.12.3.422 195 PR Plant operating at SS cond. at 90% pyr. SU7-0017 5.2 14.2.12.3.42.3 195 TM1 Heater drain pumps tripped. SU7-0017 6.7

~ 14 2.123.423 195 TM2 Plant variables recorded. SU7-0017 6.8 142.12.3.42.4a 195 AC Reacts & turbine must not trip. SU7-0017 92.1 142.123.42.4b 195 AC Safety inj. is not initiated. SU7-0017 922 14.2.12.3.42 4c 195 Act Steam generator relief valves don't lift SU7-0017 9.2.3 142.123.42.4c 195 AC2 Safety valves sha11 not lift. SU7-0017 923 142.12.3.42.4d 195 Act Pzr. relief valves do not lift. SU7-0016 92.4 14.2.12.3.42.4d '195 AC2 Safety YalYes do not lift SU7-0016 92.4 142.123.42.4e 195 AC No manual controi req. to bring to SS. SU7-0016 9.2.5 14 2.12.3.43 1% TI Cal. of Steam & FY flow Instr at Pvr tst SU7-0018.X X = 1 to 5 14.2.12.3.43.l a 196 OB Calibrate steam flow trans. agst FV flow SU7-00182 1.1 3 l

... . . KG&E Page 20 CHAPTER 14 TEST ABSTRACTS 01/09/85 Document PO TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 14.2.123.43.lb 1% OB Per. cross-check ver. of FV & SF signals SU7-00182 1.1 3 14.2.12.3.432a 196 PR Test equibmer.t calibrated. SU7-0018.X 5.1 142.12.3.432b 196 PR Plant at steady state for each pvr level SU7-0018.1 5.3 14.2.12.3.43.3a 196 TM Yerify calibration of steam flow. SU7-0018.1 6.12 3 142.12.3.433b 196 TM Compare steam & FV flow values SU7-0018.X 6.0 142.12.3.43.4a 1% AC Mismatch alm. doesn't act at 30-100% pvr SU7-0018.X 9.3 142.12.3.43.4b 1% AC1 Steam flow indication within 4% at 75%. 507-0018.4 9.4 142.123.43.4b 1% AC2 Steam flow ind. within 4% at 100%. SU7-0018.5 9.4 142.12.3.43.4c 1% ACI FV flow within 2.5% at 75 & 100% SU7-0010.4 9.5 3 142.12.3.43.4c 1% AC2 Steam flow within 3.0% at 75 & 100%. SU7-0018.4 9.6 3 14.2.12.3.44 197 Tl Nuclear instr. Sys. Test SU7-SE01 14.2.12.3.44.1 197 OB verify NIS prforms func. prior to CL SU7-SE01 1.1 142.12.3.44.2a 197 PRI NIS is insialled, calibrated & aligned. SU7-SE01 5.2 14.2.12.3.44.2a 197 PR2 NIS is operational for at hast 4 hrs. SU7-SE01 5.3 142.12.3.442b 197 PR Plant at ambient temp & psr. SU7-SE01 5.4 14.2.123.4434 197 TM1 SR indicator alarms function. SU7-SE01 62,6.3 142.12.3.443a 197 TM2 IR indicator alarms function. SU7-SE01 6.4 14 2.12.3.44.3b 197 TM1 Pyr. range test proper meter ind. SU7-SE01 6.5 14.2.12.3.44.3b 197 TM2 Power range func. of comparator. SU7-SE01 6.6 142.123.443b 197 TM3 Power ran.ge func. of rate cire. SU7-SE01 6.7 142.12.3.44.3c 197 TM1 High voltage circuitry of SR tested. SU7-SE01 6.1.1 142.12.3.44.3c 197 TM2 HV circ. of inter. range chan. tested. SU7-SF01 6.1 2

.14 2.12.3.44.4 197 ACI Control & indication func. verified. SU7-SF01 9.2.1 14 2.123.44.4 197 AC2 Reactor trip stpt of the NISS verified. SU7-SF01 9.1.1 m

.. KG&E Page1 FSAR SITE ADDENDUM 01/09/85 Document P0 TYPE C0ftilTMENT PROCEDURE SECTION(S) NOTE 14.0 CH APTER 14 14.2.2.3 4 StaffinvolYed in initial testing. ADM 01-70 3.0 14.2.4.5 _10 (1) Plant Mgr. has overall test program resp ADM 01-70 3.1 14.2.4.5 10 (2) Staff ensures plant safe while testing. ADM 01-70 3.3 14.2.4.5 104 PSRC review program before next plateau. ADM 01-70 5.2.2 14.2.8 10b Use of Rx operating & test experience. ADM 01-31 All 18.0 CHAPTER 18 18.1 1.2 3 Human factors review prior to core load. 7 18.1.18.2 3 Natural Circulation Testing. 10 3.0 CH APTER 3 Appendix 3A 1 ----

Personne1 training / certification. ADM 05-402 Appendix 34 3a Staff qualified to ANSI /ANS 3.1 ADM 01-70 5.0 Table 9.7r 1 ---

Fire Prot. available prior to fuel load. ADM 13-103 ALL 11 V115 0640.3ve 1 Review test results prior to exed. 2595. SU7-S012 5.1 S008 l

l l

I 4

KO&E Pega1

  • REG GUIDE 1.68 01/09/85 Document PG COMMITMENT PROCEDURE SECTION(S) NOTE RG 1.68 App A 2.0 13 Ensure Tech specs are satisfied. ADM 02-300 RG 1.68 App A 2.0 13 Monitor flux during coreloading. SU7-0002 6.1 RG 1.68 App A 2.0 13 Ensure prerequisites are satisfied. SU7-S009 5.1 RG 1.68 App A 2.0 13 Periodic data collection SU7-0002 6.1 RG 1.68 App A 2.0 13 fuel /Contr component properly installed. SU7-S009 6.2 RG 1.68 App A 2.0 13 Pred.of Rho to evaluate resp to loading SU7-0001 5.5 RG 1.68 App A 2.0 13 Crit / action for uaexpected response. SU7-S009 4.1.X

'RG 1.68 App A 2.0 14 Requirements for ops of sys/ component SU7-S008 ALL RG 1.68 App A 2.0 14 SR0 supervises core loading SU7-S009 4.1 RG 1.68 App A 2.a 14 Verify S/D margin of fully loaded core. SU7-0001 7.1 RG 1.68 App A 2.b 14 CR v/dravel & insert speeds SU7-SF02 6.0 RG 1.68 App A 2.b 14 CR v/drevel and insert sequences SU7-Sf02 6.0 RG 1.68 App A 2.b 14 CR position indicator SU7-SF04.X 6.0 X= 1,2 RG 1.68 App A 2.b 14 CR protective interlocks SU7-SF01.3 6.0 RG 1.68 App A 2.b 14 CR control functions SU7-SF02 6.0 RG 1.68 App A 2.b 14 CR alarms SU7-SFOX 6.0 3 RG 1.68 App A 2.b 14 CR scram time: HZP & no-flov SU7-SF03.1 6.0 RG 1.68 App A 2.b 14 CR scram time: HZP v/flov SU7-Sf 03.2 6.0 RG 1.68 App A 2.b 14 CR scram time: hot v/flov. SU7-SF03.3 6.0 RG 1.68 App A 2.b 14 CR scram time: hot & no-flov. SU7-Sf03.4 6.0 RG 1.68 App A 2.b 14 Scram time v/in 2 sigma limit SU7-Sf03.X 6.0 X=1-4 RG 1.68 App A 2.b 14 Yerify proper ops of decelerating device SU7-Sf03.X 9.0 X=1-4

! RG 1.68 App A 2.b 14 Retest at least 3 times if a rod fails SU7-Sf03 X 6.0 X=1-4 RG 1.68 App A 2.c 14 Demonstrate proper trip points end logic SU3-SB01 i

L

KG&E Pege 2

. '. REG GUIDE 118 01/09/85 Document PG COMMITMENT PROCEDURE SECTION(S) NOTE RG 1.68 App A 2.c 14 Demonstrate ops of scram breaker & valve STS IC-746 RG 1.68 App A 2.c 14 Demonstrate ops of manual scram fn. SU7-Sf03.X 6.0 X=1-4 RG 1.68 App A 2.d 14 RCS ieak rates are v/in limits STS88-004 RG 1.68 App A 2 e 14 RCS Baron concentration sampling SU7-SJ01 6.3, 6.4 RG 1.68 App A 2.f 14 RCS flov test / vibrations are acceptable SU3-8B14 RG 1.68 App A 2.f 14 RCS pressure differential as designed 30 RG 1.68 App A 2.f 14 Piping reactions are as designed SU3-BB14 RG 1.68 App A 2.f 14 Measure flow coastdown: loss of flow test SU7-8806 6.3 RG 1.68 App A 2.g 14 Cal of SRinstrumentation SU7-SE02.1 6.2 RG 1.68 App A 2.g 14 Yerify proper ops of SR & IR alarms SU7-SE01 6.0 RG 1.68 App A 2.g 14 Yerify ops of SR & IR protective funct. SU7-SE01 6.0 RG 1.68 App A 2.h 14 Mech. tests ofincore monitors. SU7-SR03 6.0 RG 1.68 App A 2.h 14 Electrical tests ofincore monitors. SU7-SR04 6.0 RG 1.68 App A 3.0 14 INITIAL CRITICALITY RG 1.68 App A 3.0 14 Neut flux continuously monitored SU7-S011 6.3 RG 1.68 App A 3.0 14 Neut count rate >1/2 before S/U SU7-S011 6.3.2 RG 1.68 App A 3.0 14 Signal-to-noise ratio >2 SU7-SC01 9.5 RG 1.68 App A 3.0 14 Required sys are operable and ready SU7-S011 5.0 RG 1.68 App A 3.0 14 CR v/ drawn before Boron dilution SU7-5011 6.3 RG 1.68 App A 3.0 14 CRinsertionlimits are observed STS CR-001 RG 1.68 App A 3.0 14 Criticality predictions provided SU7-S011 5.17 RG 1.68 App A 3.0 14 Crit / action if plant deviates from pred. SU7-S011 6.3 RG 1.68 App A 3.0 14 Rx protection sys operable & ready SU7-S011 5.0 8 RG 1.68 App A 3.0 14 Emerg S/D sys operable & ready SU7-S011 5.0 8 RG 1.68 App A 3.0 14 Normal CR v/drevel sequence SU7-S011 6.3.0

- _ _ _ _ _ _ _ - _ l

KO&E Pago 3

  • 4 .

REG GUIDE 1.68 01/09/85 Document PG COMMITMENT PROCEDURE SECTION(S) NOTE i RG 1.68 App A 3.0 15 Rho additionis prescribed SU7-S011 6.3 RG 1.68 App A 3.0 15 Ensure Periodis > 30 see SU7-S011 6.3 RG 1.68 App A 4.0 15 LOW-POWER TESTING RG 1.68 App A 4.0 15 Lov power test < ST> SU7-S011 6.4 RG 1.68 App A 4.a 15 Boron & MTC over applicable ranges SU7-S011 6.6 1

I RG 1.68 App A 4.b 15 CR & CR bank vorth ensure 1 and 2 belov SU7-S011 6.6 RG 1.68 App A 4.b 15 1: In accordance with design prediction SU7-S011 9.2.4 RG 1.68 App A 4.b 15 2: Confirm rod insertionlimits SU7-S011 9.2.4 RG 1.68 App A 4.c 15 Pseudo-rod-ejection test SU7-S011 6.6 RG 1.68 App A 4.d 15 Adequate overlap of SR & 1R SU7-SE02.3 6.0 RG 1.68 App A 4.d 15 Proper ops of SR&lR protective function SU7-SE01 6.0 RG 1.68 App A 4.d 15 Proper ops of SR&lR alarm SU7-SE01 6.0 RG 1.68 App A 4.e 15 Flux distr. for comparison v/ prediction SU7-S011 9.0 RG 1.68 App A 4.f 15 Neut.and gamma rad surveys SU7-0016 6.0 RG 1.68 App A 4.g 15 Resp. of process & effluent rad. monitor S03-SP01 RG 1.68 App A 4.h 15 Demonstrate capability of Chem contr sys SU4-RM01 RG 1.68 App A 4.1 15 CR v/drawal and insert sequence SU7-SF02 6.0 kG 1.68 App A 4.1 15 Demonstrate ops of CR block fn. SU7-SF01.3 6.0 ,

RG 1.68 App A 4.J 15 Capability of prim containment vent. sus SU7-0907.2 6.0 RG 1.68 App A 4.k 15 Demonstate ops of steam-driven Aux sys STS AL-103 RG 1.68 App A 4.1 15 Ops of main & branch steamline valves STS AB-201 RG 1.68 App A 4.1 15 Demonstrate ops main steam bypass valves STS A8-205 RG 1.68 App A 4.m 15 Demonstate ops of MSlYleakage contr N/A RG 1.68 App A 4.n 15 Demonstate ops of contr room computer SU8-RJ0X X=1,2 5 RG 1.68 App A 4.0 15 CR scram tiue at rate temp. SU7-SF03.X X= 3,4 L- .. .. -

r

,, , KG&E Page 4

- .'. REG GUIDE 1.68 01/09/85 Document PG COMMITMENT PROCEDURE SECTION(S) NOTE RG 1.68 App A 4.p 15 Ops of PZR relief valves STS BB-204 RG 1.68 App A 4.p 15 Ops of main steam relief valves STS AB-205 RG 1.68 App A 4.q 15 Ops of RHR STS EJ- 100 RG 1.68 App A 4.q 15 Ops of steam dump valves STS AB-205 RG 1.68 App A 4.q 15 Ops of turbine bypass valves STS AB-205 RG 1.68 App A 4.r 15 Ops of RCS purfication & cleanup sys STS CH-002 RG 1.68 App A 4.s 15 Vibration mess.of RCS & Rx vessel SU3-8814 RG 1.68 App A 4.t 16 Natural circulation test SU7-0024 6.0 RG 1.68 App A 4.u 16 Ops of major / principal contr sys as appr SU7- AB01.1 6.0 RG 1.68 App A 5.0 16 POWER ASCENSION TESTS RG 1.68 App A 5.a 16 Pover coeficient at 25% S07-U008.1 6.0 RG 1.68 App A 5.a 16 Power coefficient at 50% SU7-0008.2 6.0 RG 1.68 App A 5.a 16 Power coefficient at 75% SU7-0008.3 6.0 RG 1.68 App A 5.b 16 Nuc design parameters at 25% SU7-SR02 6.0 RG 1.68 App A 5.b 16 Nuc design parameters at 50% SU7-SR02 6.0 RG 1.68 App A 5.b 16 Nuc design parameters at 75% SU7-SR02 6.0 RG 1.68 App A 5.b 16 Nuc design parameters at 100% SU7-SR02 6.0 RG 1.68 App A 5.a 16 Power coefficient at 100% SU7-0008.4 6.0 RG 1.68 App A S.c 16 N/A to PWR.

RG 1.68 App A 5.d 15 Controlling Xenon transients. 32 RG 1.68 App A 5.g 17 CR Sequence SU7-Sf02 6.0 RG 1.68 App A 5.g 17 CR v/drawal block SU7-Sf 01.3 6.0 RG 1.68 App A 5.e 16 Psuedo-rod-ejection. SU7-Sf 09.X 6.0 X= 1,2 RG 1.68 App A 5.f 16 High vorth rod insert & v/drawal at 50%. SU7-Sf09.2 6.0 RG 1.68 App A 5.h 17 N/A 5

t KCAE Pege 5 REG GUIDE 1.68 01/09/85 Document PG COMMITMENT PROCEDURE SECTION(S) NOTE RG 1.68 App A 5.f 16 High vorth rod insert & v/drevel et 50%. SU7-SF09.2 6.0 RG 1.68 App A 5.h 17 N/A 5 RG 1.68 App A 5.1 17 In-&Ex-core inst detect rod misalign 50% 5 RG 1.68 App A 5.1 17 In-&Ex-coreinst rod misalignment *100% 5 RG 1.68 App A 5.j 17 N/A to PWR.

RG 1.68 App A 5.K 17 Ops of ECCS high-presinjection. SU3-EM02 RG 1.68 App A 5.1 17 Capebility of RHR

  • 25% STS EJ-100 ,

RG 1.68 App A 5.m 17 RCS ops in accordance with design. 5 RG 1.68 App A 5.1 17 Turbine bypeos sptem SU7-AB02 6.0 RG 1.68 App A 5.1 17 Atm steem dump valves STS A8-205 RG 1.68 App A 5.1 17 N/A to PWR RG 1.68 App A 5.1 17 Turbine bypass system SU7-AB02 6.0 RG 1.68 App A 5.n 17 8eseline data for LPMS. SU3-S901 RG 1.68 App A 5.m i7 RCS opsin accordance with design. 5 RG 1.68 App A 5.1 17 Atm steem dump valves STS AB-205 RG 1.68 App A 5.0 17 Proper resp Rx coolantleek det.sys. 3 RG 1.68 App A 5.1 17 N/A to PWR RG 1.68 App A 5.p 17 Yibration monitoring Rxinternels. SU3-8814 RC 1.68 App A 5.q 17 Ops felled fuel detection sys et 25%. CHM 03-070 RG 1.68 App A 5.q l7 Ops failed fuel detection sys et 100%. CHM 03-070 RG 1.68 App A 5.r 17 Computer receives correct input at 25% 5.,35 RG 1.68 App A 5.r 17 Computer receives correct input at 50%. 5,35 RG 1.68 App A 5.r 17 Computer receives correct input at 75%. 5,35 RG 1.68 App A 5.r 17 Computer receives correct input et 100%. 5,35 RG 1.68 App A 5.s 17 Calibrate & verify T-eve contr.at 25% SU7-Sf06.2 6.0

,, ,, KG&E Page 6 REG GUIDE 1.68 01/09/85 Document PG COMMITMENT PROCEDURE SECTION(S) NOTE RG 1.68 App A 5.s 17 Calibrate & verify T-ave contr. at 50% SU7-SF06.3 6.0 RG 1.68 App A 5.s 17 Calibrate & verify T-ave contr. at 75%. SU7-SF06.4 6 0 RG 1.68 App A 5.s 17 Calibrate & verify T-ave contr. at 100%. SU7-SF06.6 6.0 RG 1.68 App A 5.s 17 Cal & verify auto Rx contr e 25% SU7-SF07.2 6.0 RG 1.68 App A 5.s 17 Calibrate & verify auto Rx contr at 50%. SU7-SF07.3 6.0 RG 1.68 App A 5.s 17 Cal & verify auto Rx contr 975% SU7-SF07.4 6.0 RG 1.68 App A 5.s 17 Calibrate & verify auto Rx contr at 100% SU7-SF07.5 6.0 RG 1.68 App A 5.s 17 Calibrate & verify boron add sys at 25%. 9 RG 168 App A 5.s 17 Calibrate & verify boron add sys at 50%. 9 RG 1.68 App A 5.s 17 Calibrate & verify boron add sys at 75%. 9 RG 1.68 App A 5.s 17 Calibrate & verify boron add sys at 100% 9

~ RG 1.68 App A 5.s 17 Cal & verify integrate contr at 25% ' SU7-SF06.2 6.0 RG 1.68 App A 5.s 17 Cal & verify integrate contr at 50% SU7-SF07.3 6.0 RG 1.68 App A 5.s 17 Cal & verifyintegrate contr at 75% SU7-SF07.4 6.0 RG 1.68 App A 5.s 17 Cal & verifyintegrate contr e100% SU7-SF07.5 6.0 RG 1.68 App A 5.3 17 Calibrate & verify pzr contr. sys at 25% SU7-0009.1 RG 1.68 App A 5.s 17 Calibrate & verify pzr contr sys at 50% 6 RG 1.68 App A 5.s 17 Calibrate & verify pzr contr sys at 75% SU7-0009.2 RG 1.68 App A 5.s 17 Calibrate & verify pzr contr sus at 100% SU7-0009.3 RG 1.68 App A 5.s 17 Verify main, aux. feedvater @ 25% SU7-0018.2 6.0

.RG 1.68 App A 5.s 17 Verify main, aux.feedvater e 50% SU7-0018.3 6.0 RG 1.68 App A 5.s 17 Yerify main, aux.feedveter e 75% SU7-0018.4 6.0 RG 1.68 App A 5.s 17 Yerify main, aux.feedvater e 100% SU7-0018.5 6.0 RG 1.68 App A 5.s' 17 Yerify steam pres contr et 25% SU7- A801.3 6.0 RG 1.68 App A 5.s 17 Verify steam pres contr at 50% 6

KO&E PIga 7 REG GUIDE 1.68 01/09/85 Document PG COMMITMENT PROCEDURE SECTION(S) NOTE RG 1.68 App A 5.s 17 Yerify steam pres contr at 75% SU7- AB01.5 RG 1.68 App A 5.s 17 Yerify steam pres contr at 100% SU7- A801.6 RG 1.68 App A 5.s 17 Yerify makeup / letdown contr sys at 25% 9 RG 1.68 App A 5.s 17 Yerify makeup /letdovn contr sys at 50% 9 RG 1.68 App A 5.s 17 Yerify makeup / letdown contr sys at 75% 9 RG 1.68 App A 5.s 17 Yerify makeup / letdown contr sys at 100% 9 RG 1.68 App A 5.t 17 Ops of pzr & steam relief valves STS AB-201 5 RG 1.68 App A 5.t 17 Ops of atmospheric steam dump valves. STS AB-205 5 RG 1.68 App A 5.t 17 Ops of turbine bypass valves SU7-AB02 6.0 RG 1.68 App A 5.t 17 Ops of turbine stop & conir valves 5 RG 1.68 App A 5.0 17 Response time of MSlY and branch lY SU3-AB04 5,7 RG 1.68 App A 5.v 17 Yerify main steam & feedvater sys at 25% SU7-0018.2 6.0 RG 1.68 App A 5.v 17 Yerify main steam & feedveter sys at 50% SU7-0018.3 6.0 SU7-0018.4 6.0 RG 1.68 App A 5.y 17 Yerify main steam & feedvater sys at 75%

RG 1.68 App A 5.v 17 Yerify main steam & feedvater sys 100% SU7-0018.5 6.0 RG 1.68 App A 5.v 17 Demonstrate 80L margins for cooling sys SU7-0907.6 6.0 RG 1.68 App A 5.x 17 Demonstrate margins aux sys used v/ESF SU7-0907.6 6.0 RG 1.68 App A 5.y 17 Cal & verify calorimetricinstr e 25% SU7-SC03.2 6.0 RG 1.68 App A 5.y 17 Cal & verify calorimetric inst e 50%. SU7-SC03.4 6.0 RG 1.68 App A 5.y 17 Cal & wrify calorimetric e 75%. SU7-SC03.5 6.0 RG 1.68 App A 5.y 17 Cal & verify calorimetric @ 100%. SU7-SC03.8 6.0 RG 1.68 APP A 5.y 17 Cal & verify RCS flow inst 25%. $U7-SC03.2 6.0 RG 1.68 App A 5.y 17 Cal & verify RCS flov inst. 50%. SU7-SC03.4 6.0 RG 1.68 App A 5.y 17 Cal & verify RCS inst. 75%. SU7-SC03.5 6.0 RG 1.68 App A 5.y 17 r0! & verify RCS flovinstr e 100% SU7-SC03.8 6.0

KG&E Page8 REG GUIDE 1.68 01/09/85 Document PG COMMITMENT PROCEDURE SECTION(S) NOTE RG 1.68 App A 5.y 17 Cal & verify RCSinstr

  • 25% SU7-SC03.2 6.0 RG 1.68 App A 5.y 17 Cal & verify RCSinstr e 50% SU7-SC03.4 6.0 RG 1.68 App A 5.y 17 Cal & verify RCSinstr e75% SU7-SCO3.5 6.0 RG 1.68 App A 5.y 17 Cal & verify RCS instr e 100% SU7-SC03.6 6.0 RG 1.68 App A 5.y 17 , Cal & verify RCS tempinstr e 25% SU7-SF06.2 6.1 RG 1.68 App A 5.y 17 Cal & verify RCS tempinstr e 50% SU7-Sf06.3 6.0 RG l.68 App A 5.y 17 Cal & verify RCS tempinstr e 75% SU7-Sf06.4 6.0 RG 1.68 App A 5.y 17 Cal & verify RCS temp instr e100% SU7-SF06.6 6.0 RG 1.68 App A 5.y 17 Cal & verify incore/excore instr e25% SU7-SE02.4 6.4 RG 1.6E App A 5.y 17 Col & verify incore/excore instr e 50%. SU7-SE02.6 6.4 RG 1.68 App A 5.y 17 Cal & verify incore/excore instr e 75% SU7-SE02.7 6.4 RG 1.68 App A 5.y 17 Cal & verify incore/sxcore instr e100% SU7-SE02.9 6.4 RG 1.68 App A 5.z 18 Demonstrate process & effuent rad detect SU3-SP01 RG 1.68 App A 5.aa 18 Ops of chem & radiochem contr sys e 25% 9 RG 1.68 App A 5.aa 18 Ops of chem & radiochem contr sus e 50% 9 RG 1.68 App A 5.as 18 Ops of chem e radiochem cont sys e 75% 9 RG 1.68 App A 5.8a 18 Ops of chem & radiochem contr sys e 100% 9 RG 1.68 App A 5.bb 16 Neut. & gamma ray survey at 50% . SU7-0016 6.0 RG 1.68 App A 5.bb 18 Neut & gamma rey survey at 100% SU7-0016 6.0 RG 1.68 App A 5.cc 18 Ops of gas /lig vaste processing SU3-HA01 5 RG 1.68 App A 5.dd 18 Remote shut down of Rx SU7-0014 6.0 i

RG 1.68 App A 5.ee 18 Ops of prim contain. inert.& purg. sys SU3-GT01 RG 1.68 App A 5.ff 18 Ops ofimportant vent /AC sys at 50% SU7-0907.4 6.0 RG 1.68 App A 5.ff 18 Ops ofimportant vent /AC sys at 100% SU7-0907.6 6.0 l l

RG 1.68 App A 5.gg 18 N/A l l

l

KG&E Page 9

. . REG GUIDE 1.68 01/09/85

! Document PG COMMITMENT PROCEDURE SECTiON(S) NOTE l RG 1.68 App A 5.hh 18 Load sving test at 25% SU7-0009.1 6.0 RG 1.68 App A 5.hh 18 Load sving test at 50% 6 RG 1.68 App A 5.hh 18 Load sving test at 75% SU7-0009.2 6.0 RG 1.68 App A 5.hh 18 Load sving test at 100% SU7-0009.3 6.0 RG 1,68 App A 5.ii 18 Plant response to limiting RCP trip 100% N/A 6 RG 1.68 App A 5.jj 18 Resp to loss of turb-gen /offsite pover N/A 6 RG 1.68 App A 5.kk 18 Resp to loss feedvater heaters SU7-0017 6.0 RG 1.68 App A 5.11 18 Resp to turbine trip at 100% SU7-0011 6.0 RG 1.68 App A 5.mm 18 Resp to auto closure of all MSIV N/A 6

- RG 1.68 App A 5.nn 18 Resp to fullload rejection SU7-0011 6.0 RG 1.68 App A 5.00 18 Yerify piping & component expansion SU7-0015 6.0 RG 1.68 App C 2.a.0 21 PRESEQS TO FUEL LOAD RG 1.68 App C 2.a.1 21 Duties are specified 7 RG 1.68 App C 2.a.2 21 Evac alarms & vent contiare operable SU7-SE01 6.2.9 ,

RG 1.68 App C 2.a.3 21 Status of systems is specified SU7-S009 5.0 RG 1.68 App C 2.a.4 21 Inspection of fuel SU7-S009 5.15

~

RG 1.68 App C 2.a.5 21 Nuc instr is cal & operable SU7-SE01 6.0 RG 1.68 App C 2.a.5 21 Instr properiglocated SU7-0001 6.0 RG 1.68 App C 2.a.5 21 Audible indication SU7-0002 4.4 RG 1.68 App C 2.a.6 21 Nuc instr response check SU7-SC01 6.0 RG 1.68 App C 2.a.7 21 Status of containmentis specified SU7-S009 5.21 l

RG 1.68 App C 2.a.8 21 Status of Rx vessel is specified SU7-S009 5.0 RG 1.68 App C 2 a.9 21 Min vessel veter level is specified SU7-S009 5.9 RG .68 App C 2.a.10 21 Coolant circulationis specified SU7-S009 5.12 RG 1.68 App C 2.a.11 21 Emerg boron addition sys is operable SU3-SA03 l t

n

.. . . , KG&E Page 10

  • - REG GUIDE 1.68 1

01/09/85 Document PG COMillTMENT PROCEDURE SECTION(S) NOTE RG 1.68 App C 2.a.13 22 Status of protection equip verified SU7-S009 5.0 RG 1.68 App C 2.a.14 22 RCS vater quality SU7-S009 5.9 RG 1.68 App C 2.a.15 22 fue11cading boron concentration SU7-S009 5.11 RG 1.68 App C 2.b.0 22. PROCEDURE DETAll RG 1.68 App C 2.b.1 22 Loading sequence SU7-0001 6.0 RG 1.68 App C 2.b.2 22 Display maintenance SU7-0001 6.0 RG 1.68 App C 2.b.3 22 Proper seat & orientation of assemblies SU7-S009 6.2 RG 1.68 App C 2.b.3 22 Visual check of eachloaded assembig SU7-S009 6.2 RG 1.68 App C 2.b.4 22 N/A to PWR RG 1.68 App C 2.b.5 22 Nucinstr & nuet source requirements SU7-0002 5.0,6.0 RG 1.68 App C 2.b.6 22 flux monitoring SU7-0002 6.0 RG 1.68 App C 2.b.7 22 Expected subcritical behavior SU7-0002 6.3.1 RG 1.68 App C 2.b.8 22 f /A to PWR RG 1.68 App C 2.b.9 22 frequency of boron sampling SU7-0001 6.1.3.1 RG 1.68 App C 2.b.IO 22 Flux monitoring during suspension SU7-0002 App 8 RG 1.68 App C 2.b.I1 22 Maintenance of Voice comm SU7-0001 6.0 RG 1.68 App C 2.b.12 22 Min crev required for fuel loading 7 RG 1.68 App C 2.b.12 22 Min of two where fuelis handled 7 RG 1.68 App C 2.b.13 22 Crev vork tirac < 12 hrs ADM 01-023 RG 1.68 App C 2.b.14 22 Approvals required for procedure changes ADM 01-022 RG 1.68 App C 2.c.0 22 LIMITATIONS & ACTIONS RG 1.68 App C 2.c.1 22 Criteria for stopping fuel loading SU7-S009 4.1 RG 1.68 App C 2.c.2 22 Criteria for emeg boron injsetion SU7-S009 4.4 RG 1.68 App C 2.c.3 22 Criteria for containment evac SU7-S009 4.1.5 RG 1.68 App C 2.c.4 22 Action if fuel damaged EMG-E6

[

KO&E Page 11

~ *

- . REG GUIDE 1.68 01/09/65 Document PG COMMITMENT PROCEDURE SECTION(S) NOTE RG 1.68 App C 2.c.5 22 Action / approvals for resuming loading SU7-S009 4.3

- RG 1.68 App C 4.0 23 POWER ASCENSION TEST PROCEDURES RG 1.68 App C 4.a 23 Conduct all test at thier plateau SU7-S008 6.0 RG 1.68 App C 4.b 23 Examine radial flux SU7-SROX 6.0 X=1,2 RG 1.68 App C 4.c 23 Rx power by heat bclence SU7-SC03.X 6.0 X=1-6 RG 1.68 App C 4.d 23 Reset high 11tx trip prior to ascending SU7-S008 4.4.1 RG 1.68 App C 4.e 23 Ops of plant systems SU7-0907.X 6.0 X=1-6 RG 1.68 App C 4.f 23 Check for unexpected radiation SU7-0016 6.0 RG 1.68 App C 4.g 23 RCS leak check STS BB-004 RG 1.68 App C 4.h 23 Review of test at test plateaus SU7-S008 1

T

. . *. < . .

  • KG&E P;ga1 FSAR VOLUME 11 01/09/85 Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 0640.11.(2)2.a Shutdown margin verified by Cb SU7-0001 7.1 Q640.11.(2)2.b Contro1 rod withdrav/ insertion spds, seq SU7-SF02 6.0 0640.11.(4.).4.b Verify rod vorths SU7-SF08 6.6 0640.11.(4.).4.c Pseudo-rod-ejection test SU7-SF09 6.0

- Q640.11.(4.).4.e Determination of flux distribution SU7-SR01,2 6.0 0640.11.(4.).4.f Neutron and gamma rad survey determin SU7-0016 6.0 Q640.11.(4.).4.j Demonstrate capability of ctmt vent sys SU7-0907 7.1 0640.11.(4.).4.t Natural circulation test SU7-0024 6.0 0640.11.(5).5.bb Conduct neutron and gamma surveys SU7-0016 6.0 0640.11.(5).5.f Have a rod drop test SU7-SF03.X 6.0 3 Q640.11.(5).5.ff Demon ventilation sys maintain des temp SU7-0907 7.1 Q640.1 t .(5).5.g Control rod protective interlocks checkd SU7-SF01.2 6.0 Q640.11.(5).5.i Verify operab of rod pos ind sys SU7-SF04.1 6.0 3

%40.11.(5).5.1 Verify rod misalignment > tech specs SU7-SF09.2 9.1.4 0640.11.(5).5.kk Resp when FV htrs bypassed v/i desion SU7-0017 6.0 0640.11.(5).5.1 Demonstrate capab to remove decay heat SU7-AB02 6.0 Q640.11.(5).5.mm Demon plant reps for MSIV close at 100% SU7-0011 60 0640.11.(5).5.nn Derron plant reps from gen trip at 100 % SU7-0011 6.0 0640.11.(5).5.s Verify AFS,hotve111ev,stm pres ctri sys SU7-0011 6.0 3 0640.11.(5)5.v Verify perf of MS and FV sys SU7-0907 7.1 3

- 0640.11.(5).5.v Verify concrete temp at pentrations SU7-0907 7.1 Q640.11.(5).5 9 Verify proper oper of Incore instrument SU7-SR04 6.0 0640.11.(5).5.y Verify oper of instr /sys for heat balr.ce SU7-SC03 6.0 0640.11.1.b.(1) - -

Contro1 rod drive system operation test. SU7-SF01.4 6.0 0640.11.1.e.(5) - -

Steam extraction operability test. SU7-0907 6.1

.s . .. KG&E Page 2 FSAR VOLUME 11 01/09/85 Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 0640.11.1.j.(11) -- --

Test traversing incore probe system. SU7-SR03 6.0 0640.11.1.J.(13)

Test incore nuclear instrumentation. SU7-SR04 6.0 Q640.11.1.J.(25)

Verify computer calculations = Tech spec SU8-RJ0X X=1,2 35 0640.11.1.j.(5).5.r -- --

Verify computer calculations = Tech spec SU8-RJ0X X=1,2 35 Q640.11.1.j.(8) -- -

Demon rod entri during pyr. asc. testing SU7-SF05 6.0 Q640.12.(16) Derive MTC and meet acceptance criteria SU7-0007 6.0 0640.12.(17) Demon step and ramp respons at 50% power FSAR App 3A RG1.68 R 2 0640.12.(18) Rods <.ut of 2-sigma limit drped 3 times SU7-SF03.x 6.0 3 Q640.12.(2) Final acceptance of FV pumps SU7- A801.4 6.0 -

Q640.18 Plant vent sys main ESF gear v/i design SU7-0907 7.1 0640.2 --

(a) Source range greater than 1 or 2 eps. SU7-S011 6.32 0640.2 --

(b)- Prior to startup commencement. SU7-S011 6.3.2 0640.2 -- -

Sign >l to noise ratio greater than two. Sil7-SC01 9.5 06402 -- --

Predict estimated critical conditions. SU7-S011 6.3 0640.2 - --

Approach to criticality less than I dpm. SU7-S011 6.3 Q640.29 Evacu alarm heard in high noise areas SU7-0907 6.2

. . . . , KG&E Page 1

- PREOP COMMITMENT REVIEW 01/09/85 Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE 11.3-3 TABLE O G ASE00S VASTE PROC NST DESIGN PARAMS SU3-HA01 11.5.2.1.5 4 R AD MONITOR POST-REFUELING C AllBR ATION 8,16 182.1.1 3 RC VENT YLYS TESTED LAY ASME SEC XI 13 18.2.17.6 2 75 PORY PD CONTROLLER LOGIC CF18 REV 6 i

3.1.7 37 CTMT ISOL AT10N YALVE OP TESTING STS KJ-001 13,18 4.4.3.5 27 LOAD FOLLOVING Y/1 RCP OUT OF SERYlCE 17 62.5.4 14 PERIODIC TESTING OF H2 G AS ANALY2ER STS CR-001 19 6.2.6.3 5 CLOSED SYSTEM PERIODIC TYPE A TESTS STS-KJ-001 13,18 6.3.4.1.2 31 ACCUMUL ATOR CHECK VALVE TESTING 13 6.5.222 6 AUX BLDG TEMP M ANT AINED.) 60 DEG F 15 7.3.8.2 39 ESF AS SYSTEM TESTING REQUREMT( 3 PGS) 20 7.6.4 4 ACCUMUL ATOR YLV CLOSED TNE LIMITS 13 7.7-1 TABLE O PL ANT CONTROL SYSTEM INTERLOCKS 15 7.7.1 1 RX CNTRL SYS LO AD CHG/ TEMP / PRESS CNTRL SU7-0009.X X=1-3 7.7.1 2 RX CNTRL SYS AL ARM INDICATIONS SU7-SF01.J 6.7.16

. 7.7.1 2 RX CONTROL SYSTEM INTERLOCKS 31 7.7.1.3.3 8 ROD INSERTION LIMIT AL ARMS SU7-SF01.3 6.7.16 8.3.1.12 7 ESFAS CRCUlT BKR/ CONT ACTOR OPER ATION STS-KJ-001 21 8.3.2.2.1 38 8 ATTERY SURVEILL ANCE REQUREMENTS STS MTXX 3 9.3.4.1.2 32 CVCS CAN M AINTAIN RCS 02 & PH IN LMITS STS CH-002 34 9.3.42.2 52 ROD SHTDN LN STPT ALRM FOR EMG BORATION SU7-SF01.3 6.7.16 9.3.62.1 73 EVAPOR ATOR BORON CONCENTR ATION CEN 00-020 9.4.3.1.2 32 MAIN STE AM TUNNEL TEMP LIMITS SU7-0907.X 6.0 9.4.3.1.2 32 AUX BLDG TEMPERATURE LNITS 15 9.4.6.1.2 65 TEMP LIMITS OF AREA BELOV PRESSURIZER SU7-0907 6.0 22 t .)

(.

KG&E Page 2 l

, , a, , ,, %

PREOP COMMITMENT REVIEW 01/09/85 l Document PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE Q492.31 1 RCP FLOV/DP TEST D ATA .SU7-SC03.X X=4,5,6 14 VC82.1.3 5 345 KV BRE AKER REQUREMENTS SUS-MA01 YC9.5.22.1 6 CBX B ATTERY B ACKUP SYSTEM 15 YC9.52.4 7 COMMUNCATION SYSTEM TESTNG SU4-QF01

KO&E O

    • , SER 01/09/85 t PG TYPE COMMITMENT PROCEDURE SECTION(S) NOTE

-- 22.2 IIB.3 9 PASS capability demonstrated SU3-SJ01 22.2 III.1.1 15 GS6,7 AFS properly aligned ADM 02-102 3 I

I i

t i

l m

T:

. ;. o, Footnotes

'1) Not used.

'2) Not used.

3) There are steps, sections, or procedures that also meet this comitment but space does not permit including th e here. .
4) Not used.
5) See FSAR Volume 11, NRC Correspondence, Section 640.
6) See FSAR APP 3A (Reg. Guide 1.68)
7) Not procedurally controlled but comitment is satisfied.
8) As required by Technical Specifications.
9) Denonstrated by continuous operation.
10) _ Covered by training.
11) Satisfied during testing of individual components.

12)- System turnover verifles component. testing.

'13) ISI Pump and Valve program.

14) Will be included in the next revision of this procedure.

-15) Design feature only; does not require testing.

16) The following STS satisfy this comitment:

IC-456 IC-457 IC-458 IC-459 IC-474 A/B IC-475 A/B IC-476 A/B

17) Not allowed by Technical Specifications.
18) See also:

STS BG-205 STS EG-201

-STS EJ-205 STS EJ-206 L _

4 < 1 4

19) See STS IC-912/913.
20) See the various I&C and Operations STS's concerning ESF.
21) . Also see the following STS's concerning ESF.

KJ-005 A/B KJ-006 IC-930 EN-004'

22) This comitment is addressed in its current revision.
23) See also SU7-0001 and SU7-S009.
24) Failure to meet acceptance criteria is programatically addressed.
25) Not procedura11 controlled by an SU7.
26) HFT completed in 1984.

~27) FSAR change initiated.

28) SU7-0024-is an optional test. Currently being revised with modified Westinghouse analysis.
29) Not used.
30) Generic design (i.e. Westinghouse Form Loop PWR) satisfies this .

comnitment.

31) Included in the current revision at SU7-SF01.3/SF02,
32) Xenon oscillation is controlled by design (see FSAR 4.3.1.6 Para. 6).
33) The following STS's satisfy this commitment.

IC-450 A/B IC-452 A/B IC-453 A/3

-IC-454 A/B IC-455 A/B

-34) Also see CHM.02-230.

35) Computer points are tested with SU8-RJ01/RJ02, which are currently being performed. During the power ascension program various' points are monitored in the test procedures using computer trend blocks.

r

-

Retrieved from "https://kanterella.com/w/index.php?title=ML20129D042&oldid=2889849"