Text

Forwards Resubmittal of Various CRD Orificing assembly- Related Repts Submitted w/850131 Ltr.Certain Pages Erroneously Omitted from Original During Reproduction Process
	ML20106F623
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/03/1985
From:	Gahm J; PUBLIC SERVICE CO. OF COLORADO
To:	Johnson E, Martin R; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
	P-85046, NUDOCS 8502140031
	Download: ML20106F623 (2)
	v • d • e

{{#Wiki_filter:_ Public service company *eCehndo ~ V 16805 WCR 19 1/2, Platteville, Colorado 80651 - February 3,1985 Fort St. Vrain Unit #1 P-85046 Mr. Robert Martin, Regional Administrator U. S. Nuclear Regulatory Commission 611 Ryan Plaza, Suite 1000 Arlington, Texas' 76011-Attention: Mr. E.- H. Johnson

SUBJECT:

Resubmittal of Various CRDOA Related Reports

REFERENCES:

(1) PSC Letter, Lee to NRC RIV Regional Administrator, dated 1/4/85 (P-85003) -(2) NRC Letter, Martin to Lee, dated 1/17/85 (G-85024)' .(3) PSC. Letter, Lee to NRC RIV Regional Administrator-dated 1/28/85--(P-85030)' (4) PSC Letter, Gahm to NRC RIV Regional Administrator dated 1/31/85 (P-85040)

Dear Mr. Martin:

Attached please find a complete resubmittal (including attachments) of our letter P-85040, dated January 31, 1985, concerning Public Service Company of Colorado's response to commitments made in the. ~ L letters referenced above. Certain pages were erroneously-omitted from our original submittal' during the reproduction process. Please discard our original submittal and replace with the attached. B502140031 850203 I I fDRADOCK 05000267

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+ e ,f., + -+ u t ,.5-n r. j-s -g.. ~ - If; you? have!-anyE:l questions _ orf comemnts ~ regarding. the' - attach'ed ' Ldocuments,'p. leas'e-contact-Mr. Mike Holmes:at (303)~571-8409. -Sincerely,, .Y i y - J. W..~Gahm 1 j_ Manager, Nuclear Production? F Fort St.1Vrain Nuclear nGenerating Station-1- JWG:FJN/alk

Attachments i

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y + ~ 4 public Service Compan.y of?(CeBondo. ^ g wm i* 16805 WCR 19.1/2, Platteville, Colorado '80651 o 1 .i i' -January 31,-.1985- -Fort St. Vrain Unit #1-P-85040 Mr. Robert Martin,_ Regional' Administrator. I U. S. Nuclear Regulatory Commission 611 Ryan Plaza, Suite 1000 Arlington, Texas 76011 Attention: Mr.-E. H. Johnson

SUBJECT:

Submittal'of Various CRD0A Related Reports

REFERENCES:

(1) PSC Letter, Lee to NRC RIV 2 Regional Administrator, dated 1/4/85.(P-85003) ' (2) NRC Letter, Martin to Lee, dated 1/17/85 (G-85024) (3) PSC Letter,-Lee to NRC RIV Regional Administrator dated 1/28/85 (P-85030) i

Dear Mr. Martin:

1 In response to commitments -made in the referenced letters, Public Service-Company of Colorado ' submits the. attached ' reports. and procedures for Nuclear-Regulatory Commission review. The attachments ~ .are summarized as follows: I - Control Rod System Operability Evaluation Report - Control Rod. Drive' and~ Orificing Assembly Refurbishment Program Report - Control Rod Drive and Orificing Assembly Proposed Preventive / Predictive _ Maintenance Program Report --- i. -Attachment 4 - Control.. Rod -- -Drive. and-Or.ificing- ' Assembly- -Refurbishment Program'. Radioactive : Waste-Hahdling Analysis Report ' Attachment 5 - Control Rod ~ Drive.and Orificing Assembly Interim - Surveillance Program! Report - QCA n a l n Con o N O U(pl/ UQ} '

'1 - 2 s 4 ~ ? Attachment 6.- Wattmeter-Use.to Determine InsertedLEAbsorber. String-Position Report-Attachment;7 - Exerpt.from-Issue -15 of S0P.12-01 describing operator actions to prevent overdriving of control . rods past the rod-in limit. . - Operations ~0rder No 84-17 describi..g operator: actions upon a loss of purge flow and/or detection of high moisture levels in the primary _ coolant. ~ 4 - Current CRD Temperature Data Collection procedure-. which. requires Station Manager notification cupon- ~ discovery of a measured CRD temperature in excess-of 250'F. d If.you have any questions or comments regarding-these documents, please contact Mr. Mike Holmes at (303) 571-8409. . Sincerely, .h w J. ahm Manager, Nuclear Production Fort.St. Vrain Nuclear-Generating Station JWG:FJN/alk Attachments .l \\ - \\. t 4 kt b i .) [ -.

ATTACHMENT 1 -T0 P-85040-4 CONTROL R0D SYSTEM OPERABILITY EVALUATION-PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN-NUCLEAR GENERATING' STATION PREPARED BY: 2 V Mark 6./Jodfeph Technical -SYrvices Engineer APPROVALS: M Q J.\\ JK JEggebraten-Technical Services Engineering Supervisor , (V. '4; J. Novachek' Technical / Administrative Services Manager (~ %%/ P/ l %v v 3~ v 1

~ s CONTROL R00 SYSTEM' OPERABILITY.. EVALUATION. TABLE OF CONTENTS' ABSTRACT INTRODUCTION 'I. FSAR REVIEW.................................................;2_ A. SYSTEM DESCRIPTION................................... 2 B. D ES I GN BAS ES........................................... 2 Control Rod...................................... 2 D r i v e M e c h a n i s m.'.................................. -4 Rod Control And Position Indication.............. 6 C. ESSENTIAL-SAFETY FUNCTIONS AND COMPONENTS'............. 8 D. CONCLUSIONS.......................................... 13 c II. TECHNICAL SPECIFICATION REVIEW............................ 15 A. LCO, SR 0VERVIEW...................................... 15 i B. CONCLUSIONS AND RECOMMENDATIONS-...................... 19 III. CONTROLLED DOCUMENTS REVIEW................................ 21 A. SAFETY RELATED LIST.................................. 21 B. CONCLUSIONS.......................................... 23- - FSAR Scram Parameters . - Technical Specification. Scram Instrumentation Requirements , - Technical Specification Scram Surveillance hequirements 1 -i i r

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m g -CONTROL ROD SYSTEM-0PERABILITY EVALUATION. ABSTRACT: This1 report : summarizes Lthe results of a detailed review and evaluation of the existing licensingLbasis forethe reliabilityL of the Fort St. Vrain Control Rod System. All FSAR; design and, safety considerations were reviewed-.to -identify -the significant,. design bases, and the essential safety functions and components. required' Lfor accident-fanalyses. 10nce identified,- -these' functions and components were evaluated for consistency with . Technical-Specification. requirements, controlled. documents ~ and procedures,.and plant-operational ^ experience.- In-general, the licensing basisiwas found to be consistent with . Technical . Specification requirements and. design: documents.

However,

' specific

changes, additions, 'and evaluations are recommended in maintaining the original level-of reliability ~ in view of plant operational experience.and.

continuing engineering investigations. INTRODUCTION: This report is organized' to highlight <the three main areas-reviewed in evaluating the licensing basis for control rod reliability: FSAR REVIEW, TECHNICAL SPECIFICATION REVIEW, and CONTROLLED DOCUMENTS REVIEW. Specific conclusions and recommendations are included following the review-of each area. i 4 4 9 _1 \\

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I.

FSAR REVIEW A.' SYSTEM DESCRIPTION The control rod system functions to control and safeguard the fission process occurring in the reactor. The main components -of the -control rod system consist of the control: rod, the drive mechanism, and the_ control and position indication circuitry. The control rod consists: of eleven (11) boron carbide cannisters and a tube type _ shock absorber attached. along

a. metal spine suspended in'the core from steel cables.

The design considerations are specifically described in: FSAR-Section 3.8.1.2. The important-design. considerations are related to boron content, rugge.iness - of design, and component design life assumptions. ~The drive mechanism primarily consists-of the drive motor, motor break,' reduction gearing and bearings,' guide

pulleys, cable drum,_ limit, switch cams, position potentiometers, guide tubes, and a velocity. limiting three phase capacitor array.

These components..are discussed in FSAR Section 3.8.1.1. The drive' mechanism is designed to be fail-safe under all postulated accident and operating conditions, allowing for free-fall ' gravity insertion at all times. The rod control and position indication system consists of the automatic and manual

controls, associated circuitry, interlocks, power sources, sensors, and various relays, which provide for normal reactivity control and indication as well as ~ bnormal reactor a

protective actions. Reactivity control is described in FSAR Section 7.2.2, and protective actions in Section 7.1.2. The automatic and manual-scram capabilities are considered essential. B. DESIGN BASES The primary -FSAR design bases and major assumptions for ensuring the reliability of the control rod system have been identified as listed. The design bases which are considered essential for performance of the scram safety function, as identified by accident analyses, have been identified by an asterisk (*). Control Rod t 8

1.

Individual boron loadings are 0.48 gm/cm for the 8 inner nineteen (19) and 0.63 g/cm for the outer eighteen (18) rod

pairs, 30 and 40 wt. %

respectively(3.8.1.2,3.5.3.1). - L

~ ,w-. , 3.y y, 4:n + 7 g N j h

2.

The i overalli control _: rodLworth andl configuration, considering. fuel and-poison loadings,'must.be -able-7 i to ensure.subcriticality,; with a minimum shutdown-f

' margin of'0.01 AK, underL all. conditions-withthe' ~ - maximum ' worth rod-pair withdrawn i(3.2.2.3,{ 3.5.3.I', 3.2.3.2). (See Technical' Specification LCO 4.1.2.)-

3 The cstructura1(. integrity, flexibility, and overall'

~ dimensions'will be maintained while exposed? to.the. normal' - reactor 1 operating' en'vironment, :such;'that. . satisfactory operation, helium flow,'and freei. fall insertion are' sustained (3.2.2.6, 3.8.1.2). 4

4.

The normai operating environment for the control. rod; will not exceed.~ 1300'F - (3.8.1.2) or. 10vpm-total (oxidant. impurities (CO,L : CO2, H2O) during normal continuous ' operation :(A.9.2.1,-. 4.2.1, 3.2.3.3, 3.2.3.5)..(See LCO 4.2.10,4.2.11)

5.

The crushable tube-type shock absorber ~1s designed' to absorb the energy of a falling control. rod, due to cable' or spine failure, such that the integrity-i of the baron cannisters and bottom reflector element. l 1s maintained (3.2.2.6, 3.8.1.2). 6. The design'11fe of the control rod is six (6) cycles (1800 effective full power days-(EFPD)) of full. ~ j-power operation (3.8.1.2).

7.

The maximum rod pair, worth. in 'the event of an j accidental rod pair withdrawal, during. all anticipated configurations, will result in a transient less severe than-the reactivity accidents evaluated in Section 14.2(3.5.3.1).

8.

Under the design environmental conditions, the clearances, low drag force s,- and dry film j lubrication make the probability of galling or binding of the cables in the. guides extremely. unlikely (3.8.2). 1 9. Cable fatigue life calculations show-a life of 4 approximately 1 x 10' jogs.

10. The-control rod is designed to withstand the maximum seismic disturbances :or Design Basis: Earthquake ~,.

withoutlossoffunction(3.8.2). R. 1 1 y +-. yam, w p .,,,,.n.,-,----7-. e-,m 'w.

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1.

The. control rod drive mechanism provides for free-fall, rod insertion under lossVof AC motor or-DC-brake power conditions'_(3.2.2.6F3.8.1.1). 2.' The JCRD motor rotates-under the; influence of'a. capacitor array to: limit the speed-~of control rod insertion during gravity driven scram conditions (3.2.2.1,3.8.1.1). 3. Environmental operating conditions are maintained ~ within' acceptable limits based-on design, thermal' barriers, radiation shielding, and normal' operation _

of the penetration. purge - flowi and -liner cooling systems-(3.8.1.1).

-4. Radiation shielding and primary coolant activity. levels are. designed.to ' limit drive-mechanism radiation levels ~to 1 rad /hr.under norma 1' continuous operating conditions.(3.8.1.1.1).

5.

The maximum temperature-. rating: of the._ drive mechanism which might inhibit the scram function is 272*F. 6. The normal penetration purge flo is designed to be approximately 5 lb/hr/ penetration. 7. Presence of foreign particles and.-_ debris,- both metallic and molybdenum disulfide, was observed during the original ~ prototype testing. However, it was specifically evaluated and determined to have no significant effect on drive performance based on design provisions 'which limit ingress. and accumulation.

8.

All bearing and gear materials, fabrication, and' special dry film' lubrication-have been_ " proven through ex_ tensive _te_ sting to maintain-satisfactory operation in the purified: helium ~ environment (3.8.1.1.1).

9.

Gravity free fall capability is based on - an initiating load of 120 lbs. per cable (Page 3.8-5). I

10. The drive mechanism is designed to withstand the maximum-seismic disturbance or. Design. -Basis Earthquake without loss of. function (3.8.2).
11. The total scram insertion time is approximately.

152 seconds (3.5.3.1). > w +,v'-w-s- ~- " w -s c ~mn" o=m,n-s-- -av., v e-g s--+-- ~e

a -xmg .g .a : ? s '*12.'The -maximum reactiUity Linsertion. rate -lis -ibout 0.001 AK/ft, based on a normal' complete ~ red pair:- withdrawal. time of :approximately; l180-seconds ~ (3.5.3.1',. 3.6.7). '

13. Operation ~ of the control < rods by 'the control rod drive system,~; including' representative inumbersLfor

scram operations, fis possible 'for at least the :six -

cycle (1800~EFPD) minimum. life of the control rods' + (3.2.2.6). -14.-The' prototype testing, initiated to ascertain the reliability of 'the control. rod system, simulated -the -expected long f? term. operating conditions-of' temperature and= helium,,with less-than 10 VPM

oxidant, impurities, 'and no radiation effects. LIn the' shim mode,- the prototype-demonstrated some 200~ years of service life or-.33 times its expected service life (6 years) (A.9.2.2).

15. The' rod drives were to receive inspection ~ and-refurbishment as necessary (A.9.2.2).

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1.

A-rod withdrawal' sequence interlock prevents rods from being withdrawn' out of sequence at power levels - between 1 and 5% rated power - (3.5.3.1, 7.1.2.2, '7.2.2.1)..(See Technical Specification LCO'4.1.3) 2. The control and position-indication' system.is. utilized to establish and measure-the core power level (7.2).

3.

Partial control rod insertion is' required to prevent endangering fuel : particle integrity for region peaking factors greater than~1.83 (3.2.3.1). (See Technical Specification LCO 4.1.3) 4. The ' runback' controller is allowed to insert rods only(7.2.1.2). 5. Rod control actuator switch-interlocks and power supply load sensors ensure'that not more than one rod pair 'may be moved simultaneously-' outward. (7.2.2.1,7.2.2.3). 6. Each of the thirty-seven (37) control rod drives is equipped with two (2) potentiometer type position transmitters, one providing continuous analog. indication for each rod and one providing digital indication on a selective basis in the control room (7.2.2.3,7.2.2.1). 7. In addition to Item 6 (above), each rod pair is equipped with three pairs of s limit switches which provide control room indic'ation of individual full in/ full out position, outward /inward rod motion, and. slack cable (7.2.2.1, 7.2.2.2, 3.2.2.6, C.13). ~

8.

Means must be included in the control room to monitor and control the reactivity status of the-reactor (7.2.2.1, C.13.1). (See: Technical: Specification LCO 4.1.8) 9. Excessive deviation between rod pairs in a group is alarmed for rod. deviations greater than 2 ~ 1 ft'- (Page '3.6-19, Page 7.2-9 and Section 7.2.2.1).

10. To prevent undesirable flux and temperature distributions, partial rod insertion,.with the exception of the regulating rod pair, shall be limited to two groups at any position (separated by at least' 10 ft), six pairs up to 2 ft, and the two runback groups (six pairs) at any position-not to exceed 4 hours (3.2.3.1).

(See Technical Specification LCO 4.1.4) ' 9 y J

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11. The automatic scram' circuitry-provides 5 three-

-independent -sensing: circuits. for zeach-scram . parameter, and -is.. based on.a general 2'of 3 logic- . system up to the final trip logic (7.1.2.1).

12 ' Direct 1 ~DC

. brake : power supply ~1nterruption is. i provid.'d .through Manual Scram capability, indepensent of the automatic system (7.1.2.1).

13. Relays in the 1 rod - brake : circuitry ~deenergize contactors in the rodfmotor circuit to ensure scram

-functions (7.1.2.1). 14.~ Manual push-button bypass circuitry is provided to allow' powered insertion of a bound rod. following a-scram (7.1.2.1)..

15. Remote manual scram' capability is provided in the switchgear room to effect. plant shutdown in the event the control

' room-becomes uninhabitable (7.1.2.3).

16. The reactor mode switch (RMS)

.-is' provided as a backup to manual-scram (7.1.2.3).

17. The automatic scram parameters are defined as shown in Attachment 1 to this report (Table 7.1-2).

e t D, b

y 4 C. ' ESSENTIAL SAFETY FUNCTIONS' AND COMPONENTS Through review of the FSAR~ accident analyses, with respect to1 J the previously listed design bases, essential safety functions and components have been identified along :with = general ~

conclusions.regarding accident evaluations.

Environmental Disturbances (Sections 14.1, 1.4, and 10.3) Of all the FSAR accident evaluations, the environmental disturbance accidents are probably the most significant in terms of the impact on equipment requirements. All plant structures, systems, and components have been divided into two groups, Class I and Class II, based on their importance to. safety during. environmental' accidents. Of the environmental accidents, the Design Basis Earthquake and Maximum Tornado were considered limiting. Class I equipment was specifically defined-through evaluation of an encompassing accident involving a-Design Basis Earthquake or Maximum Tornado, which are evaluated to include the failure or loss of: -outside electric power, main turbine, deaerator, all three boiler feedpumps, all condensate pumps, auxiliary boiler and backup auxiliary boiler. feed pumps, main conder.ser, main and service water cooling towers, and pipin;; and equipment downstream of the main steam bypass valves. Under these conditions, items whose failure or damage could have resulted in:

1) Release of abnormal quantities of radioactivity,

11) Interference with safe reactor shutdown, or tii) Interference with adequate removal of decay heat, were designated Class I.

The Class I list included certain considerations for redundancy, accident mitigation, and single' failures whereconsideredappropriate(10.3.10). The minimum requirements for cooldown of the plant under these conditions have been defined by another list of. equipment items termed Safe Shutdown, which is a subset of the Class I List (10.3.9 and 14.4.2). Thus, all Class I items, with the exception of the fuel handling machine, are designed to withstand both the Design Basis Earthquake and the Maximum Tornado without unsafe damage or loss of safety function. (See Design Documents SR 6-1 and SR 6-2) All other plant structures, systems, and components were designated Class II..

s e -The " control and orificing assemblies" are considered Class I - and the_" control rod drives" are considered required fcr safe shutdown cooling, as designated in T:ble 1.4-1 ~and 1.4-2 respectively.. The ability of the control rod to-: drop freely into the core under worst case core misalignment conditions following an earthquake, is specifically . evaluated in Section 14.1.1. .The' conclusions of Section 14.4.2 regarding acceptable safe shutdown cooling, assume that a scram is achieved immediately following the event. This is consistent with Section'7.3.9,'which requires immediate reactor -shutdown following seismic instrument indication that a disturbance of the magnitude of the Design Basis Earthquake, 0.10g, has occurred. The critical safety functihns, for these conditions, would be those responsible for the scram functions. Scram, under the postulated conditions, can be assumed to occur automatically or manually within ten minutes after the event, as evaluated in Sections 10.3.3 and 10.3.1, respectively. (See Technical Specification LCO 4.4.1) 8 9 9 0 f r ! l

.m.. IReactivity Accidents (Section 14.2) The FSAR. evaluated l reactivity accidents initiated.by any of the following conditions: -1. Excessive removal of control poison, 2. Loss of fission product poisons, 3. Rearrangement of core components, 4. Introduction of steam into the core, and 5. Sudden decrease in reactor temperature. From these evaluations, it is concluded that the accidental = withdrawal of control poison results in the worst reactivity accidents. . Ten specific protective actions or lines of defense against the rod withdrawal accidents are provided, of which nine are considered effective during a startup accident, and five effective during power operation. The. inherent protective design features considered are the maximum reactivity addition rate of 0.00009 AK/sec., and the available scram reactivity, which is always sufficient to achieve suberiticality with a 0.01 AK shutdown margin with due regard for inoperable rod pairs. (See Technical Specification LCO 4.1.2) 9 9 9, -J

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[l[ 4 N 5 4 Three' main ' od withdrawal. accidents are specifically reviewed: e r 1). Maximum Worth Control Rod Pair Withdrawal :at.' Full; Power,: ii) Maximum Worth Control-Rod' Pair Withdrawal at Source Power,, and tii). Simultaneous 1 Withdrawal >of, All Thirty-Seven -Rod-

Pairs.,

i)"1The. power rance.accidentassumed'three'sequentiaI' ' lines of defense:. automatic scras' at 140t : rated ~ power as initiated by.~the power' range channels,

manual scram after 60 seconds, and hot' rehett' steam temperature' automatic scram: at ;.1075'Fx after 105:

seconds. Only1when protective action. is inot initiated

prior.- to the 1075'F reheat steam temperature limit is fuel. failure assumed to -occur.: However, it is concluded'that~ the 2*4 fuel particle failure would result in less than design primary.

coolant activity levels; and core shutdown /cooldown-and PCRV integrity would 'notEbe' impaired. (See Technical Specification LCO'4.4.1)'

11) Assuming the -sequential -fatlu're of four specified

-lines of' defense,the source-power accident was assumed terminated by a scram' at.140*4 rated power.- The-consequences of a-0.047 AK source'- power insertion was evaluated with' no fuel particle failure expected. (See Technical Specification LCO 4.1.3) tii) The simultaneous rod pair withdrawal accident (57) was considered incredible due:-to the' specific protective design features including -control rod acutator switch interlocks, and rod motor ~ power supply line load. sensors. For the; limiting. conditions of 0.0029 Ak/sec. -reactivity' insertion,- 180 second total withdrawal time, and 150 second. rod insertion time,-a scram initiated at'140r power will not lead to fuel failure nor~any other condition endangering the safety of the' plant..(See Technical Specification Surveillance Procedu'res SR 5.1'.la-A/5.4.1.4.4.b-R-Load Sensor, -Scram and Withdrawal Rate,and5.4.1.4.4.a-P-HandSwitchInter. locks) S Eh t [

n __ Design Basis Accidents (Sections.14.10 and 14.11) For-Design Basis Accident No. 1, (permanent Loss-Of Forced Circulation,.the FSAR assumes an automatic scram on "two loop trouble" occurs =upon-initiation of the' event. Following scram, the_ core ' fission product afterheat.-is expected to-result in peak temperatures of 2980'C for the center of the active core. The boron compact loadings of 30 and 40' wt 'for inner and outer rods, were specifically evaluated and determined to maintain the structural integrity of -the boron compacts thus ensuring that no major _ loss of. poison material would occur (D.3.3). The' analysis-of Design _ Basis Accident No. 2, Rapid Depressurization, assumes that automatic scram is. initiated by the load programed PCRV pressure - Low, 50 psig below normal or 650 psig,from full load. Neither the event initiation nor conditions following_'the event ~are considered to impair the reactor shutdown systems, control rods and reserve shutdown material. (See Technical Specification LCO 4.4.1 Scram Parameters snd Settings) Steam Leak Accidents (Section 14.5) For the various limiting steam generator leaks analyzed in the FSAR, automatic scram is assumed to occur following correct operation of any one of three safeguards: high moisture (2 inputs), high pressure, or manual steam generator dump and scram. These scram parameters are assumed to-be operable to initiate corrective action within approximately 100 seconds following the event. (See Technical Specification LCO 4.4.1) Other Accidents Other abnormal conditions such as loss of purge flow (14.6.1.1), cable failure (3.8), and loss of power have been evaluated and determined not to impair the shutdown function of the control rod system. In the incredible event of total inoperability of the control rod system, the reserve -shutdown system is adequate and independently redundant to achieve shutdown conditions from any operating condition (3.8.3). (See Technical Specification LCO 4.1.6 and SR 5.1.2) 1 -

--- m-D; , CONCLUSIONS 1. Although the control rod. system was adequately evaluated to remain fail-safe under11oss of _ purge-flow conditions, purge flow was a ~ design consideration for normal,. continuous power operation for minimizing the effects of primary coolanti in-the CRD motor area..Therefore, the proposed orifice motor plate and window' seals will be installed to reduce purge flow requirements. 2. Due to the concerns regarding control rod temperature, control-rod temperature will be monitored on a regular basis. 3. The control rod cable failure and corrective actions should be evaluated for impact on FSAR design' life and operating environment assumptions. A 10CFR50.59 Safety Evaluation has been written for changeout of the material. 4. The FSAR specifically considered both the ability to . differentiate between rod motor withdrawal and insertion characteristics, anc the ability to identify bound rois by measuring rod motor characteristics. The proposed-watt-meter and Back-EMF testing capabilities are being evaluated and formalized for use in predictive / preventive maintenance programs. 5. Control Rod Drive refurbishment efforts have specifically identified as left acceptance criteria for design considerations related to position indication, primary and secondary penetratiori seal' leakage and scram time. 6. CRDOA serial numbers will be verified and tracked to assure inner and outer ring boron loadings are maintained in accordance with the DBA-1 analysis. 7. Recent investigations have determined that the major consideration in the observed failures to scram was long term control rod drive degradation. 'From FSAR design life considerations, the control rod absorber section was considered the limiting factor. The control rod shock absorber was later defined as the limiting component of the control rod, due to neutron embrittlement.. Once the design life of the control rod shock absorber was identified (1800 EFPD), the drive mechanism was then prototype tested for performance over this expected service life. However, actual operating experience has s shown that normal degradation of the drive . occurs independently of. EFPD accumulation. Periodic CRDOA performance monitoring will be implemented to provide adequate information to detect significant degradation. I

~~ - 8. Since-all l11miting' . accident analyses assume Ethat fautomatic or manual -scram is-initiated early? Ein the accident,. performance degradation type failure would not need ta-be addressed provided that periodicg testing and-preventive / predictive maintenance- ' programs

are

' mplemented. -Therefore, accident. reanalysis -i s-not i necessary. . 9. The reserve-shutdown system was designed to provide an alternate, independent means of shutting the reactor down from any operating condition without movement of the-control-rods. To ensure this capability, examination of reserve shutdown ' material will be included as'a part of the CRDOA preventive maintenance = program to overify that-material bridging or agglomeration is not occurring. i 9 k

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~ ) v s.? -II. ETECHNICAL' SPECIFICATION REVIEW- ' A.- LCO, SR OVERVIEWJ The' Technical-Specification..requirementsj and- ' corresponding procedures related to the control rods - and the Lreserve shutdown: system were; reviewed;to ensure that-theLidentified FSAR analyses " limits are - incorporated,. - that- 'the existing > limits are consistent' with~ FSARE analysesi'that LCO's:have appropriate' SR ; requirements,- and that SR

requirements are maintained through-appropriate SR procedures.

~ The 'LCO, SR, and SR_ procedure matrix was identifiedias follows: LCO 4.1.2 Operable Control Rods SR 5.1.1-Control Rod Drives SurveillanceL j ~ SR 5.1.la-A/ Control ~ Rod' Scram' Test / Multiple 5.4.l.4.4.b-R Rod Pair-. Withdrawal Check SR 5.1.lb-M < Control Rod Operabil.ity- ) SR 5.1.4-W-P Core Reactivity' Status Check: LCO 4.1.3 Rod Sequence SR 5.1.5 Withdrawn. Rod Reactivity Surveillance SR 5.1.5-RX Control Rod Reactivity Worth LCO 4.1.4 Partially Inserted Rods LCO 4.1.8 Reactivity Status SR 5.1.4 Reactivity Status SR 5.1.4-W-P Core Reactivity Status Check LCO 4.4.1 Plant Protective System Instrumentation See Attachment 2 SR 5.4.1 Reactor Protective' System .See Attachment 3 SR 5.4.1.1.1.a-RP, Manual'(Control Room) Scram Test SR 5.4.1.1.2.a-MP Manual (I-49)ScramTest. j I i y y. ~,,y __,.,s ..p..., .n-,.y-e 4 g

v..c .c y em, n a. .y - i t x ~

SR 5.4.1.1.3.b-P/ >.; Startupj Channel Scram 1Testi.

g ' 5.4.1.4.1.b-P. 'SR 5.4.1.1.3 c-R LStartup. Channel Scram Calibration = 'tSR 5.4.1'.1.4.b-M/ -Linear Power C'hannel'- ~5;4.1.4.2.b-M , Scram Test SR 5.4.1.1.4.c-0/- Linear Power:Channe1~ ' 5.4. I'. 4. 2. c-D - Heat Balance-Calibration ~ SR 5.4.1'.1.4.d-R/. Linear Power Range 5.4.1.4.2.d-R-Channel Calibration 4 SR 5.4.1.1.5.b-P/ Wide-Range Power-5.4.1.4.3.b-P Channel Test i SR 5.4.1.1.5.c-M/.WideiRange Channel. 5.4.1.4.3.c-M- ' Heat Balance Calibration SR 5.4.1.1.5.d-R/ Wide Range Power i 5.4.1.4.3.d-R Channel Calibration i: SR 5.4.1.1.6.c-R Primary Coolant Motsture i Scram Calibration SR 5.4.1.1.6.e-M Primary Coolant Motsture Instrumentation Sample. Flow l Alarm Functional Test SR 5.4.1.1.7.a-M Primary Coolant Moisture l Scram Test SR 5.4.1.1.8.b-M Reheat Steam Temperature-l Scram Test i SR 5.4.1.1.8.c-R Reheat Steam Temperature: Scram Calibration' p SR 5.4.1.1.9.b-M/ Primary Coolant Pressure t 5.4.1.2.9.a-M Scram Test !? SR 5.4.1.1.9.c-R Primary Coolant Pressure j Scram Calibration -e SR~5._4.1.1.10.b-M Circulator Inlet Temp. Scram Test-

p. :

- v. ~, N. a w, 5, e

m. 4 5 4 6 f 4 3 -

5 4

7 -J %... j s j t

SR ~ 5.4.1.1.10.c-R Circulator Inlet Temp.

~ Scram Calibration 3 _.SR 5.4.1.1;11.a-M Hot Reheat. Header 1 o Pressure Scram Test ISR~5.4.1.1.11.b-R Hot Reh' eat Header Pressure-Scram Calibration SR 5.4.1.1.12.a-M Main-Steam Pressure = ' Scram Test 'SR 5.4.1.1.12.b-R . Main Steam Pressure Scram Calibration SR 5.4.1.1;13.a-M Two Loop Trouble. Scram' Test SR 5.4.1.1.13.b-R - Two Loop Trouble-Scram Test SR 5.4.1.1.14.a-M Plant 480V Power . Loss Scram Test SR 5.4.1.1.15.b-M High. Reactor-Butiding Temperature (Pipe Cavity) - Scram Test SR 5.4.1.1.15.c-R High Reactor Building Temperature (Pipe Cavity), Scram Calibration LCO 4.1.6. Reserve Shutdown System SR 5.1.2 Reserve Shutdown System SR 5.1.2ad-Q Reserve Shutdown Hopper-Pressure Test SR 5.1.2a-W ACM Nitrogen. Backup Bottle Pressure SR 5.1.2bd-A Reserve Shutdown-Hopper. Low Pressure Calibration SR 5.1.2c-X . Reserve Shutdown Assembly Functiunal Test SR,5.1.2e-X Reserve Shutdown Hopper Pressure Switch Calibration SR 5.1.2f-X Refueling Penetration Examination SR 5.1.29-R-Reserve Shutdown Valve Operability Test- \\ .]

_n .,o n es..,i.,. LCO's :4.1.2 and 4.4.1 ensure that the available scram reactivity worth and automatic / manual initiating : actions-respectively, are maintained functional in accordance -with'the accident analyses of the FSAR. The scram-parameters of LCO 14.4.1 and associated surveillance requirements are attached. LCO's 4.1.3 and' 4.'l.4 defiYe design startup and' power operation requirements which must.be verified-to ensure ~ - safe power'assention and continuous power operation. LCO.4.1.4 is controlled administratively and thus does not have a specific surveillance requirement. 1 4 1 I f l- ' l t-l l t

- B. CONCLUSIONS AND RECOMMENDATIONS /

The recommendations made!below will be evaluned as a part of

-the Technical Specification Upgrade Program. 1) LCO 4.1.2 basica11y' - requires that control rods be " operable" or " fully inserted" to verify available shutdown margin. Although.the LCO states that these conditions must be met during power operation, the basis and the FSAR clearly require' that they be met at all times. Therefore, a change to the applicability of the LCO is recommended to make it consistent with the FSAR. The allowable actions in LCO 4.1.2 when ' withdrawn and partially inserted control rods' are. determined to be inoperable should be stated.along with the requirement to verify compliance within a certain period following rod inoperability. Per the basis of LCO 4.1.2, a control l rod is considered operable if it demonstrates scram ] capability or is fully inserted. 2) SR 5.1.1 should be revised to adequately address the 1 determination of scram capability for both withdrawn rods and partially inserted rods and position verification of fully inserted rods. Control rod position indication is also necessary to verify compliance with LCO 4.1.4, LCO i 4.1.8, and the basis for LCO 4.1.2. It' is therefore recommended that indication discrepancies and requirements be specified in SR 5.1.1 as well'. 3) Provisions for acceptable alternate scram capability testing and rod-in position verification testing should be added to the Technical Specifications. 4) Provisions should also be added to include periodic i checks of a representative sample of the control rod drive temperature indicators to ensure that the maximum i temperature rating of 272*F is not exceeded during power operation. 5) The criteria defined in the basis for LCO 4.1.3 are actually design safety requirements and should be contained in the Specification section so that it is j clear that these limits are not to be exceeded. 6) SR 5.1.5 for the measurement of control rod worths during cycle startup, should clearly state that a comparison' of measured and predicted rod worths is required'and that a 20% discrepancy is acceptable as i specified in the procedure. The 120% acceptance criteria should be explained in the bases. m

z 4 ,, v1 ,y' y e 0 ~' '7) :LCO'-4 1 4l:is controlled administrative 1y and thus does' ~ not have an applicable.surveillace requirement. This LCO .should specify-appropriate actions for exceeding limits . and al'.ow ' specific time periods for. achieving compliance. 8)L.All FSAR scram. parameters are' adequately controlled and tested per LCO 4.4.1 and SR 5.4.1. 9) The _ reserve ~ shutdown system -LCO, SR,- corresponding procedures, and anticipated fcorrective actions :are

- %s considered. adequate. -to_ demonstrate and -ensure the operability of the system.- However, recent problems with this system suggest the need for periodic examination of the material oto monitor and detect long term degradation.-

Technical' Specifications should be developed to require that one low and one high boron content hopper be functionally-tested on a refueling cycle basis and_that .the material collected undergo visual and-chemical examination.

- X ll. 4 ;. g. 'i + -- ^ :~ ~ ^^ '~ t-A y e 3

III.

CONTROLLED COCUMENTS REVIEW- ~ . A. SAFETY RELATED LIST Control Rod Assembly; The : control and'orificing assembly. as specified 'in FSAR : ~ p Table 1.4-1, is ': equipment ; ites - D-12012 on the' Safety: ' Related Equipment List (see Dwg. D-1201_-940). The Safety-. j Related' List includes. all_ components: which have :been-3 -- designated. Class I.n This assembly is designated:' seismic type 2, and environmental I.D. 5,- meaning that the item must function.only following ai seismic event,"and that. it is required foi safe shutdown'(Dwg.- 01200-100). Drive Mechanism' The control rod' drive mechsnism is not separately listed i in-the LSafety Related List, ~ even though- ;1t-is J-specifically listed as safe shutdown,in FSAR Table 1.4-2. This.is due to the fact that.the whole assembly -is listed I as Class I, Safe Shutdown.- However, for FSAR purposes, } it is clear that the only part of the assembly. required to remain operable for scram; capability and Safe. Shutdown, is the drive train assembly. :The. control rod absorber sections and power supplies are considered fail-safe. (See Surveillance Procedure SR 5;1.16-M) The rod motors are powered directly from'the Control Rod } Drive Motor Control Centers 1 and 2 -(N-9225, N-9226), through Reactor MCC's 1 and 3, (N-9229A, N-9231) which are all on the safety related list. 3 e f + 1 I I L f i l i f i

x-e S; o Scram Circuitry 'TheLprotective Scram Circuitry is based on hindrance logic; the protective action is caused by. loss of_ signal. The control rod brake power supply from InstrumentL Buses 1 and 2.(N-9237, N-9238), is noimally supplying. Lpower to the control rod brakes, and can be interrupted ~ by one of the:following actions: 1. A scram signal from the PPS circuitry grounds out or-de-energizes control-power to the relay coils in the brake power supply lines, which causes the contacts to open, disconnecting the brake power supply and releasing the brake mechanism (Dwgs. IB-93-6 and-0169-2951). The PPS contacts in the-brake : power supply are XM93125-1,- -2, XM93126-1, -2, and XM93127-1, -2. The manufacturer _ is-Square D, Model #CL7002-TG-2. They are listed on the safety related subtier component list as Subt-313, seismic type 1 (function both during and following a _ seismic event), environmental I.D.-3 (required for safe shutdown-located in three room control complex). (See -Technical Specification Surveillance Requirement SR 5.4.1) 2. Numerous manual. scrams may be-initiated as a backup to the automatic scrams. The three predominant methods for manual scram are: actuation of the manual scram switch, HS-9330 on I-03; positioning the Reactor Mode Switch to 0FF, HS-1216 on I-03; and depressing 2 of 3 pushbuttons in the switchgear room, HS93372, HS93373, and HS93374, cr< I-49. These hand switches are all on the safety related list and are classified as. seismic type 1, environmental I.D.-6 (Class I but not required for safe thutdown cooling-environmental qualification. required for loss of air conditioning). (See-Surveillance Procedure SR 5.4.1.1.la-RP and SR 5.4.1.1.2a-MP) In addition to de-energizing the brake circuit, the brake power supply also supplies control power to a. set of relays and contacts in the power supply circuit to the control rod drive motors. When the brake circuit is de-energized, control power to contactors K48, K49, K50, and K51 is lost, which causes their associated contacts to open, disconnecting power (120V) to the control rod drive motors. This causes any control rods which were being driven in or out, at the moment the scram occurred, to fall into the core. Contactors K484K51 are manufactured by ITE, Model A103C. They are listed in the safety related subtier component list as Subt-499, seismic type 1, and environmental I.D. 1 (ClassI not required for. safe shutdown). l 1 0 ~J

a. _jl 6 ~' tx: ~ ~ A'2cdram - bypass. circuit also. exists, - which' provides ',L the cdpability-to power drive a postulated bound or stuck. control-rod following scram actuation..The bypass circuit is norma 11y'. open and is. closed-hy actuationlof one.of four. hand-switches, HS-93475+93478,. which close. contacts:K61, K62,'K63,-and K64. These contacts and hypass circuit are considered Class I since. they provide.for a-design safety function. These contactors are manufactured by ITE, Model A103C,' and 1are listed as- -Subt-499. B. CONCLUSIONS ~ All the automatic and manual protective functions, parameters,- circuitry, contacts.and mechanisms required to achieve scram action - are on the Safety Related List.. These safety related functions were found to be ' appropriately tested ;by. plant" surveillance procedures-except for the rod drive mctor de-energizing circuit (K48+K51) and the bypass drive circuit (K61+K64,' H.iS3475+478).. These functions are not considered necessary for safe shutdown, nor. required. by ' limiting FSAR accident analyses, but appropriate plant procedures are being developed to address these safety related functions. e a 4 i

dt c= Table 7.1-2 ~@ Scram Parameters 3 mer.ai Pun Abs.iutet "3-Sensed VertableE Type end Ihm6er of Input betector Locatten Basic topic Lead Value Trip Level h3 g

14. Ilannel liendsettch(1)

Centrol Rose 1 of I Seerd(I-43)

16. Manuel Itand switches (3)

Centrol Doord I-4g 2 of 3 8 10 counts / set nuclear Channels I Il PQtvteoll 1 of 3 Neutroncountrete.hfgag) 2. (use only at fuel Lead 3. Bate of neutron flus rise high nuclear Channels Ill. IV. V PCAVtiell 2 of 3 e I decades 5 decades /sta (use only at Startaqs)& (widerange) per ute 4. Iteatron fles high sluclear Channels Ill. IV. V. PCAV isell 2 of 3 lett power 1401 poner VI. Wil. Vill .~ 2 of 3 5. Primary coolant solsture - high Beestat mentterI (8) PCRW Penetretten 2 of 3 plus e -50*F SF*r 1 of I er despelat dempoint I of 2 high Devel 6. Seheat steam temperature. high, Thorusceneles(12) Roccter tullding 2 of 3 100tT leF5T (4 theruecouples are testined for 1 scram channel) 7. Primary coolant pressure. les Pressure TrenamittersI(3) PCRW Penetrettee 2 of 3 700 pela le pel below reted (use only at remer)i programmed with teed 8. Primary seelant pressure - high PressureTransettlersh(3) PCat Penetretten I of 3 700 pela 7-1/25 eteve normel pressure programmed with lead g.' IIet rehest line pressure las Pressure settches (3) Turbine Gutiding 2 of 3 ' Sie psig 35 pelg. (use only at romerla, 14. Superheat lies pressure les Pressureswitches(3) Turbine tutiding 2 of 3 2500 pots. Iles pstg (useemiratPomer)1 11. Plant electrical systen poner. Undervettegerelays(9) 480V SuGR I of 3 400 volts 400W huses lA. 18. 8 IC less No. IA. II. 8 BC (t out of 3 phases se (2 out of 3 buses) less of voltage for 35 seceeds M 12. Tue-leep troublei toep shutdemn logic Centrol toen I of 3 3 (Seerd110) (hethleaps) g 13. Reacter hullding semperature. Thornacomples(3) Deacter Building 2 of 3 95'.lle*F 3ts*F k htWe rn 2H 2 Instatten la parenthests refers to Interlock Sequence Switch or teacser leede Suttch posittens. h same tressettlers are used for steaevuoter dump. l'Tue-teep trenkle" is a conditlen whereby one steam generator leap is shutdeun and tremele that would nomally cause a leap shutdeun is sensed in the other steen generater leep. I ctual erly setpelats are more ceanervative to allow for instriment. inaccuracy. A f 1 i

ATTACHMENT 2 Tcrt S't. Vrain #1 Technical Spe.:ifications Revision 13 - 6/29/76-Page 4.4-3 Speciffeetfen LCO L.L-1 TAILE k.k-1 INSTFJf(ENT 0?.GATI!:0 REOUIRDM TOR *LA**7 rm:.v.;IVE SYT.*M. SC?#k 'MIED2M ICNDf.t4 ' PI'. HISS!3LE TRIP OPERA 3LE.DIGREE OT BYPAES NO. FtmCTIONAL UNIT SITTI?d C.5?AUWELS R N A*:CY CONDT"IO**3 la. Manual (Control Roc =) 1 0 Enne 2 (f) 1 No: e lb Manual (Emergency Boeri) 5 2. Startup Channel-Eigh 1 10 cps 2 1 Reacter Mode Sv. in "RUH" 3a. Linear channel-High, e ikC% power 2 (f) 1 None-Channels 3. k, 5 T) 3b. Linear channel-Eigh, < Iko$ power 2 (f) 1-Kone. ,[~ Channels 6, 7, 8 It) Primary Coolant Moisture Rem Righ Level Monitor 167'F Dewpoint 1Cf,tl 1 (c) Rone No* Imop Honitor 127'F Detpoint 2/ Loop (f,tl 1Acop (h) 3 5 Reheat Steam Temperature 1 1cT5'T (a) 2 (b) (f) 1 Kone -. Eigh (b) ~ 6. Primary Coolant Pressure 1 50 psig below 2 (f) (k) 1 Less than 305 - Imv normal, load rated power programmed (a) 7 Primary Coolant Pressure 17 5% above 2 (f)-(k) 1 None - Eish no: mal rated, load progrsamed (a) 8. Bot Reheat Header 1 35 pois 2 (f.)~ 1 .Less than 3C% Pressure - Low rated laer

9. Main Steam Pressure 1 1500 Psig 2 (f) 1-Less than 30%

- Imv rated power l

10. Plant Electrical, (d) 2 (e) (f) 1 None-System-Loss 2

'l ~ Reactor mode II. Two Loop Trouble switch in . Fuel Loaddng" .]

12. Rich. Reactor BuUding 5 325'F (f) 1' None Temperature (Pipe Cavity).

\\ H c. ' j .1 1 o ,-4 :

~ f' l c I, Amoedmont No. 11 e i f Table S.4-1 e WINIMIRI s.. Ese yWR OCMS. CAL 1BAATICIIS. AIS TESTIIIG OF SCBAN 818T91 taneamel teocrietten Fenetten Freemener (1) Method 1. IIoneet (Centret Rose) e. Test R e. Menselly tely spetse

3. Iteneet (1-49) e.. Test N

e. Mennelly trip each channet 3. stort-up Chemmet e. Cheek 9 e. Ceeperleen of tee eeperate ebeenet indlestere ,8 b. Test y b. toternet test elseet to verify tripe. end eterne e. Calibrete R e. Internet test signet shall be eheeked and eelibrated to essere that its eetput to in seeerdance eith the

i deelge requiremente. This shall be done efter esoplet-

+ leg the outerest test signet procedere by eboeklog the output indleettee elene turning time laternet test signal 'l, switch.

l 4.

Lineer power Cheneet e. Cheek 3 e. Couperleen of 6 seperate ehannet indlestore ll jf N - b. Internet teet elseet to verify tripe and eterse b. Test e( ? e. Calibrate

3 e.

Channet adjested to agree eith heet betosee esteetettee d. Cellbrate R d. Internet Test signale to adjust tulpe end ledleettene i 8: l 3. Wide pense Feuer Channet' e. Cheek 9 e. Comparison of tietee seperate indlestore

b. 'Internet Test es este te verify tripe eed eieres s

b. Test p i e. Calibrate N e. Chesnel adjested to agree with heet betenee esteeletten 4. d. cettbrete R d. Internet Test signals to adjust tripe and ladleettene N 3* 6.. Frieery Coolset Meistere e. Osock .3 e. Cooperiosa of too separete high level ehemmel mirror $M. rn 3= (ett stianeete) temperature ladleettene 4 *.s x . b. Ossek 9 b. Ceeportese of sie oeperate les loset ehemmet sterer g'd gQ E QQ. temperatete indleettens ea e, +[-.m s Log. w 6""< 4h(4 M FJ 4 et $h Or Mn een e . laMN, 0 0 %D , - I 3 t::.. 'r*. 38 e

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.._..r..--....- ATTACHMENT 3 PAGE 3 Tort St. Vrain #1 . Technical Specifications Amendment 25 - 3/2/82 Page 5.4-5 l- = t

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.s ATTACHMENT ~2~ ~ T0 P-85040 ) 1 FORT ST. VRAIN CONTROL ROD DRIVE AND ORIFICING ASSEMBLY REFURBISHMENT PROGRAM 4 PUBLIC SERVICE COMPANY OF COLORAD0' FORT-ST..VRAIN NUCLEAR GENERATING STATION PREPARED BY: Ken Ewell Proto-Power Corporation APPROVAL: . - 0[O ~ / Frank 'd Novachek Technical / Administrative-Services Manager : I w e

J FORT ST. VRAIN STATIDN'- CONTROL ROD DRIVE AND DRIFICING ASSEMBLY REFURBISHMENT: PROGRAM-p PROGRAM DESCRIPTION-i I Introduction This report descr'ibes the' program currently being undertaken ati i Public Service. Company of Colorado's LFort St. - Vrain ' Generating ' Station to refurbish the reactor control' rod.crive and orificing - i ~ assemblies (CRDOA). The report includes both a1 description of. the CRDOA components to be inspected, tested,-and refurbished or i-replaced,. - as. necessary, as -a part of the program :and-a description of the procedure to' be used.for disassembly and-reassembly of the CRDOAs. LReplacement parts to be used will either be. manufactured to the i 1. original equipment specifications or be an upgraded ~ design to-resolve problems which have been experienced or anticipated. Where upgraded parts are to be-used, the changes in design 'have been. demonstrated to be suitable for the intended applications-and documented by existing design change procedures.- 4 The overall. purpose of the CRDOA refurbishment program is to ensure both that the CRDOAs will perform their. intended safety-functions and that-potential operability.' problems with the- - CRDOAs will'not limit plant availability. s. 1 l t l + 7 i ! i a i ~-. .m

2..

T 'CRDOA Comp'onents Involved-in the Refurbishment Program ~ 'The.. following CRDOA components will be inspected, tested,~and Lrefurbished or_ replaced,.as -necessary, as a' part of: the , refurbishment program: Compone'nt' l _Re'furbishment Activities -l I

1. Control. Rod Drive _

l Assembly 1 (200) Assembly 1 -l

a. Shim Motor &

l Test and rebuild or replace, as necessary ~- Brake Assembly l

b. Bearings

-l Clean or-replace, as necessary

c. Gears l

Clean, as necessary

d. Limit Switches /

l Test and replace, as necessary Potentiometers l (Replace' components previously j-l identified to be faulty.);

e. Control Rod Cables l Replace

f. Seals l

Inspect and replace, as necessary. I-

2. Orifice Control-l Mechanism l

l

a. Orifice Control l

Test and rebui-id or replace, as necessary Motor .l 1

b. Bearings l

Clean or~ replace, 's necessary a

c. Potentiometer l Test _and replace, as necessary

d. Gears l

Clean, as necessary

e. Drive Shaft & Nut [ Clean, as necessary

f. Drive Shaft l

Clean, as necessary Housing l l.

3. Rod Retract Switches l Replace-(with cables) 1

4. Cable Seals l

Clean, as necessary I

5. Control Rods l

Verify serial numbers-I

a. Clevis Bolts l Replace with Inconel bolts I

l

6. Primary Seal Ring l

Inspect and replace, as necessary I

7. Reserve Shutdown.

l System l l

a. Boron Balls l

Replace

b. Rupture Disk-l Replace, as necessary

c. DP Switch l Test and replace, ~as necessary t- -

i

] 4 r -. c ~ 2- ~l

8. Helium Purge Check l ' Test and_ replace, as necessary Valves-l l-1 In addition, the-following; design modifications.will be made'to~

l CRD0As as a~part of~the refurbishment program: a. Installation _of new purge seals fon. the orifice control mechanism mounting plate to_ improve control .of helium _ purge flow into the upper housing of the-CRDOA. b. Use of Inconel in: lieu of. stainless steel for control rod cables, cable end fittings, 'and cable-clevis. bolts to elimina'te the potential for stress I corrosion cracking in these components, c. Installation of RTDs. in. all CRDOAs.to monitor temperatures in the. vicinity of' the control rod drive assembly and orifice control mechanism. d. Installation, when required, of. replacement seal material for seals internal to the 200 Assembly and the primary seal. Refurbishment Approach The approach which will.be used to refurbish the CRDOAs was developed to meet the following program objectives: a. Ensure that safe shutdown capability is not affected-during refubishment work. b. Minimize personnel radiation exposure and Refueling Floor contamination levels, c. Ensure proper quality control 'and documentation. d. Minimize the potential for problems.

The- -refurbishment work'.will_ be. accomplished utilizing a combination of-existing plant. equipment and facilities' intended for CRDOA refurbishment (i.e., Reactor Building Crane, Auxiliary-Transfer Cask, Reactor. Isolation Valves, Shield.' Adapters, Equipment Storage Wells, and _the Hot-Service Facility), together. .with' special ' shielding, _ -tooling, ~ fixtures,

cranes, and

. ventilation equipment specifically designed to facilitate the . refurbishment program. A list of the special equipment which - wili be_.used.is provided-in Attachment 1. The following approach will be utilized for refurbishment of the CRDOAs. Detailed procedures have been specifically developed to direct' and control the refurbishment work. The appr6ach allows for a number of CRDOAs (up to five assemblies) to be refurbished in-parallel through the-use' of multiple workstations. For clarity, the.following steps describe the refurbisFment tasks for a single CRDOA. All steps.are to be performed with the reactor shutdown and depressurized. A. Overall Sequence 1. CRDOA are refurbished sequentially based ~on the availability of the Hot Service Facility -(HSF) for removal and reattachment of the control rods. e 2. The first CRDOAs to be refurbished will be the spare assemblies currently' stored in the Equipment Storage Wells (ESW). 3. The remaining CRD0As are removed sequentially from the reactor (within Technical Specification limits for rod removal) and replaced with refurbished assemblies. B. Refurbishment Procedure 1. Conduct pre-refurbishment testing to establish initial CRDOA performance. 2. Move CRDOA from ESW (or Reactor) to the west endlof-the HSF (see Attachment 2) using the Auxiliary Transfer Cask (ATC). 4 =

.l - = 3. ! Remove :the control rods' and' deposit in carousel, as =follows: a. Lower rods into carousel rod tubes.

b.

Engage rod clevis holders. c. Rotate. clevis and remove clevis bolts. -d. Cut swaged eye from each cable and deposit.in cask. t 4. Move the CRDOA from HSF-(West) to ESW using 10 ton gantry crane with Transfer Shield and position on. ESW.' stands. (Upper stand raises CRDDA sufficiently to. allow access to openings in the side of the1 upper housing' for removal of ~ control rod drive assembly. Lower stard supports.the orifice valve: assembly during disassembly of the CRD0A.) 5. Disassemble the CRD0A. a. Disconnect electrical connectors and tubing through access openings. b. Remove CRD ~ Assembly (200 Assembly) and place in cart. Move to CRD Refurbishment Area. 4 c.. Remove and dispose of' control rod cables. d. Remove rod retract switches, t e. Remove orifice control mechanism. Inspect, test, clean and refurbish the mechanism, as necessary. f. Remove the upper housing. Inspect and' replace 4 the primary seal, as necessary. A g. Remove the shield container. ~ h. Remove cable' seals. Disassemble and clean for reuse. 1 6. Refurbish the. Control-Rod-Drive. Assembly (200 Assembly). g i La. Disassemble and clean parts. i i

1 I

.n.-

m y n,- . ~ ,.4 m = b. . Reassemble -with :new ' cables and rod retract switches. Replace. bearings and : seals, :as-necessary. Test shim motor and brake assembly and replace, or rebuild,: as.necessary. c. Adjust switch and'potentiomete'r setpoints and test theLassembly. 7. ' Refurbish the orifice valve d' rive shaft assembly, Lif deemed necessary, based on. orifice valve performance and: shaft' torque measurements. ~ a. Pull shaft.with bearings. 'b. Clean shaft and bearing cartridge. c. ' Replace bearings, as necessary, d. Reassemble. 8. Reassemble the CRDOA. a. Attach-the refurbished 'CRD Assembly, upper housing, and shield container to a reassembly fixture on the 10 ton gantry crane. b. Attach cable seals and rod test weights to-control rod cables. Lower test weights into guide tubes., c. d. Install cable seals. e. Install shield container.- f. Install upper housing. g. Install orifice control mechanism Land rod retract ~ switches. h. Test orifice drive mechanism. i.- Install new purge. seals. j. Install and. test CRD Assembly. 9. Move CRDOA from the ESW to the east end of the Hot. Service Facility, using the _ Transfer Shield and 10 ton gantry crane.. t

.=. i .f- ' 10.' Replace the Reserve Shutdown: System Boron' Balls. If Vacuum out ballstthrough fill connections. a.

b.'.

Inspect chamber with.boroscope. Replace rupture. disk,'as'necessary. -c. d. Refill with'new baron ba'11s. e. Conduct pressure test. 'Tes't DP switch.. f. Remove rod test weights. Inspect.and. repair,, as necessary,- 'the -g. secondary seal. 11. Move. CRD0A from HSF (East) to HSF (West) 'using. Transfer Shield and 10 ton gantry crane. j 12. Reattach' Control Rods. Reassemble c1'evis using manipulator and clevis a. bolt wrench. b. Disengage clevis holders. c. Raise rods. I d. Rotate carousel to " Test" position. j-e. Perform CRDOA testing. 13. Move CRDOA from HSF (West) to reactor, using ATC. Install in position previously vacated by the removal of a CRDOA of similar boren loading characteristics. Perform final testing-Lin the reactor. Refurbishment Schedule ^ The CRDOA' refurbishment program is scheduled.to.begin i February 1,1985.fo11owing installation of special shielding and equipment required to support the program and training of personnel who will be performing the refurbishment activities. Refurbishment of 37 CRDOAs~ (total number of CRDOAs. in the. reactor) is scheduled to be completed by April 1, 1985. 4 7 d ), 1 . ~,,

.L, ^

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SPECIAL EOUIPHENT FOR CRDOA REFURBISMMENT 1. ' Carousel!with Rod Tubes, Clevis Holders, and Valve Support Stand - HSF(W) 2.- Shield Wall with Lead Glass Windows, Hanipulator, and Clevis. Wrench'es - HSF(W) 3. Hydraulic Cable Cutter - HSF(W) 4. Clevis Cask and Cart with Track - HSF i 5. TV. Cameras - HSF(W) 6. Decon Brush Ring - HSF(W) 7. Rotat'able Shield - HSF(E) 8. Access Platforms - HSF(E) 9. Special Lighting and Power Supplies - HSF 10. Communications System - HSF 11. Special Ventilation: HEPA Unit and Ducting - HSF 12. Airlock and Special Access Door - HSF 13. CRDOA Support Stand for ' Boron Ball Removal - HSF(E) 14. Boron Ball Container - HSF(E) i 15. Alignment Fixture for SA - HSF(W) 16. Boron Ball Removal and Fill Tools, including Air-Driven Vacuum Cleaner - HSF(E) '17 10-Ton Gantry trane with Rails 18. 1-Ton A-Frame Hoist 19. Transfer Shield with Bellows,. Lifting Frame, and HEPA Unit 20. CRDOA Support Stands (upper and lower) for Disassembly - ESW

a v-

a:94 n t 1 1 21. CRDOA Lifting Adapters-(for.200 and 600 Assemblies) ESW 22. ' CRDOA Reassembly Fixture. ESW - 23; Orifice Drive Shaft Puller - ESW- - 24.

Rod Test Weights 1-ESW 25.

CRDOA Electrical-Test-Panels 26. 200 Assembly Carts with HEPA Unit- ~ 27.- . Cable Seal Removal and Reinsta11ation Tools.

23. -

Ultrasonic Cleaners C I e 2-i, e

-.- Attachment ' 2' CRDOA Refurbishment Program .s-Hot Service Facility Special Shielding and Equipment / ~ / a r w A s. rY r

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wa,_ _ ATTACHit NT 3 LTO P-85040 CONTROL ROD DRIVE AND.- -ORIFICING ASSEMBLY PROPOSED, PREVENTIVE / PREDICTIVE MAINTENANCE PROGRAM Prepared'by: [ ( JtnfEggebroten Technical Services Engineering Supervisor. \\ Approved by: Trank ;x NovachW Technical / Administrative. Services Manager Public Service Company of Colorado 1 Fort St. Vrain Unit #1 i \\ O l - - 19 p.e pm -D 3 U % V @ V ).

^ m ~ R 2 1 -l I. - ABSTRACT' A review of: source information to identify potential preventive-maintenance activities has been completed, and aspects. of that . program are being prop'osed. The detailed implementation of;some. ) parts of the program will be dependent upon the results -of currently underway Engineering; studies. Evidence suggests that [ a preventive maintenance : schedule based on the scheduled refueling cycle - for normal service. rods'(1.e. replacement of. rods in refueling regions with refurbished asseablies), and for the l regulating rod, in conjunction with predictive maintenance, is appropriate. Of particular importance is the monitoring of i' shim motor performance, to identify and schedule maintenance. other than normally scheduled maintenance. ~II. DESCRIPTION OF TECHNICAL REVIEW A review of a variety of source information on Control Rod: Drive and Orificing Assemblies (CRDOAs) has baen performed to. identify aspects of maintenance for which preventive maintenance consideration would be appropriate. The following sources cof-information were used: 1. Operations and Maintenance Manual (GA-9806, May 1977) 2. Completed Plant Trouble Reports from the STAIRS database 3. Open Station Service Requests (Plant Trouble Reports) 4. Plant Maintenance Personnel 5. Plant Maintenance Engineering Personnel 6. Proposed Modifications 7. Operational Experience 8. D-1201 Drawings (Design Drawings) 9. Surveillance Requirements 10. . Engineering Development Studies From' this' variety of information, a set of-potential preventive maintenance activities has been identified. Each of these is being subsequently considered -individually with. regard to -component failure history,~ service life, predictive maintenance; (FDM) test potential, and other possibilities, to identify a. set i of preventive maintenance (PM) activities that is appropriate. i ~ t .,n a w w ww-m e-

n_=. 3.c =,, i j 3 .= -IIIc PREVENTIVE: MAINTENANCE (PM)- PROGRAM - GENERAL-OVERVIEW =-OF: POTENTIAL PM ACTIVITIES A. ' SHIM MOTOR / BRAKE ASSEMBLY - 1. Visual Examination-La. - Pinion gear b. Motor bearings "~ c. Brake pads + 1 2. Test - as left a. Dynamometer b. Torque to rotate - removed from CRDOA c. - Torque to rotate - installed on CRDOA d. Back-EMF. (scram generated braking. voltage) 3. Shim Motor Bearings a. Clean / replace as required 4. Electrical a. Megger motor (insulation test) b. Dynamometer (load capability). 3 c. Megger brake windings (insulation test) B. DRIVE TRAIN 1. Visual. Examination of exterior 2. Torque - delivered (rods on) measurement-a. . Torque to rotate - motor installed on CRDOA - through shim motor rotor shaft (This is the same as item A.2.c,-L above) b. Back-EMF (scram generated braking. voltage) C. CABLE-1. Visual examination 2. Surface wipe analysis 3. Replace one cable every 3rd refueling cycle to allow: a. Detailed visual examination b. Meta 11ographic examination c. Pull test e

Lc. 4 D. RESERVE. SHUTDOWN SYSTEM 1. Hopper. a. Visual examination' 2. - Material a. Sample removal - visual _ examination b. Sample analysis - select CRDOAs 3. Pressure switch a. Functional test - Surveillance Requirement-4. Valves a. None 5. RSD System a. Functional test (blow rupture disk) - Surveillance Requirement E. POSITION POTENTI0 METERS - ROD PAIR 1. Visual Inspection 2. Test 3. Replace based on service a. Number of shims b. Rod travel-c. Anomalous indication d. Other service parameters F. LIMIT SWITCHES (2 each - slack cable, in, out, retract) 1. Visual Inspection 2. Test 3. Replace based on service a. Time in reactor b. Moisture 1 c. Anomalous behavior [ l 4. _,--m_.-

1 1 5 G. ORIFICE DRIVE MOTOR ASSEMBLY l'. Visual 2. Bench Test 3. Clean and lube (dry) '4. Replace support nut H. ORIFICE DRIVE LEAD SCREW 1. -Visual - as found 2. Clean physical 3. Dye Penetrant testing 4. Lubricate and exercise I. LOWER SEAL 1. Visual 2. Clean physical, wipe 3. Clean - body housing J. PRIMARY SEAL - 600 ASSEMBLY 1. Visual - both surfaces 2. Clean - wipe 3. Clean - mating surface, penetration and 600 Assembly 4. Lifetime evaluation possible replacement. K. PRIMA.RY SEAL - 200 ASSEMBLY 1. Visual 2. Clean - wipe 3. Clean - mating surface 4. Lifetime evaluation possible replacement L. CHECK VALVES - (RSD, CRDOA Purge) 1. Visual 2. Testi

3 6 M. CABLE SEALS 1. As determined by observed elevated / abnormal housing temperatures N. ORIFICE MOTOR PLATE SEALS 1. Visual 2. Clean - wipe 0. WINDOWSEALS 1. . Visual 2. Clean - wipe 3. Gasket material - evaluate for lifetime P. MCC CAPACITORS ^ 1. Test 2. Shelf life / service life evaluation Q. ELECTRICAL - POWER 1. Megger shim motor (test insulation deterioration) 2. Bench test shim motor (load capability) 3. Megger brake windings (test insulation deterioration) 4. Bench test brake solenoid (load capability) 5. Bench test stepping motor (load capability) R. ELECTRICAL - INDICATION 1. In/Out Limit Switch Function - test redundancy when made up 2. -Slack Cable - test redundancy when made up 3. Full retract - N/A - normally not both made up S. BOLTS - EXPOSED TO PRIMARY COOLANT 1. Visual on selected bolts l

7. T. -ABSORBER STRINGS 1. ' Visual 2. . Lifetime evaluation possible replacement. 3.- ! Shock absorber only replacement IV.. PREDICTIVE MAINTENANCE (PDM) PROGRAM A. SHIM MOTOR / BRAKE ASSEMBLY AND GEAR TRAIN 1. Wattage - outward shims - as found/as left inward shims - as found/as left 2. Back-EMF voltages during scram -(and/or -~ equivalent) - as found/as left 3. Delivered torque at motor - as found/as left a. After CRD removed from PCRV during PM b. Static - complete rotation, both directions 4. Scram times (SR 5.1.la-A) a. Gross performance parameter (really monitors motor variation if done with constant capacitances) 5. Rod drop rate (SR 5.1.lb-M) a. More sensitive than Item 4., but less than Item 2. 6. Torque to rotate motor / brake assembly - as found/as left a. Removed from CRD0A (hence. reflects motor bearings only) b. Static - complete rotation I e

.x 8 7. " Dynamometer. Tests" - as found/as~left.(Technique under. development) (Note - this. test is not the same test'as indicated. ~ .before.- here.the object.is to apply a known torque input'to measure' response, especially voltage, such as occurs during scram.) a. Simulate driving' load of rod pair b. Measure response (generated EMF) c. Develop correlations i.e., ' applied torque, in oz vs. mean voltage amplitude at nominal motor speeds d. Use to trend rate of performance decline e. Use for model verification of shim motor. 8. Jog counts a. Record jog counts b. Use to assist PDM Evaluation B. TEMPERATURE i 1. Monitor shim motor temperatures 2. Determine shim-motor performance vs. temperature via voltage and wattage measurement. C. STEPPING MOTOR 1. Monitor stepping motor speed (i.e., determine the rate at which a given change in orifice valve position occurs) 2. Trend [ NOTE: Some of the above PDM actions are done while the CRDOAs 1 are installed in the reactor, some while they are being l maintained, and some under both conditions. l l l L 1

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c-- e 4 ~ 4 w e o -9. L I V. DISCUSSION 'The above PM' program should be' implemented on a refueling basis for.CRDOAs that would normally be removed'for refueling,' anda on a more frequent basis.for the regulating rod as established.from predictive maintenance activities... This would mean that a CRDOA 'in normal service would be routinely maintained on a refueling cycle rotation, unless predictive maintenance (PDM) indicated 'a need for more frequent maintenance. I Central':to.the program is the use'of predictiv'e' maintenance I techniques to monitor the most'~important: aspect: of ~.CRDOA performance,. scram capability. By. monitoring _ performancez ~ parameters indicative of train resistance and motor -load, ~ such i as wattage and generated voltage or "back-EMF" (amplitude and/or -frequency), the level of torque applied to the~ motor,.as well as ~ i the-resistance torque of the train,' could be determined.- This, i when trended and compared to.known values,. should allow- { prediction of times when maintenance will be required. -The j exact manner in which these tests will be :used 'is currently under development; it is expected that they'will be able to provide the indicated information, although complete definition .of all aspects of application and use of.the tests may require 1 some time after startup. The proposal for certain operational j aspects of.the PDM program will be implemented on a weekly basis for determination of scram capability and temperature performance during power operation. It would also be' desireable t } to collect this information during. shutdown for. trending. j purposes. Other aspects of the PDM program to support this j effort would be done during the normal'PM activitiy. j' Note that the emphasis of predictive maintenance is gear train i and motor performance,.and the preventive maintenance aspect is i on examination and refurbishment of the shim motor / brake-assembly. This is consistent with the conclusions obtained from i the vast performance testing and analysis performed following~ i the failure to scram incident of June 23, 1984, which identified i . motor bearings as the most important factor in the incident. Note also, however, that the program is designed so that any F overall reduction in mechanism performance will be corrected, i regardless of cause. Any degradation in gear train, pulley,.or other components will consequently be identified and corrected. j VI. CONCLUSION n i The basic schedule for preventive maintenance-is proposed as the original refueling basis program which. performs PM on.non-regulating CRDOAs on a 6 refueling cycle rotation, and a special schedule for the regulating CRDOA subject in-all cases to predictive maintenance results suggesting otherwise. 6 i i -s-y +, - s-_ -,. - - - -, _, -... ~.,,.-----.c,

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The preventive maintenance proposed herein, in conjunction with current and ~other. projected surveillance requirements, will assure all safety-related aspects of CRDOA performance, as well: as r.,any other operational ones. 'As indicated, many aspects 'of the proposed program involve collection of data on performance which may ultimately be used.to propose changes to this PM program.

t 4 a 4 e 6 i e ~ e

ATTACHMENT 4-TO P-85040 FORT ST. VRAIN STATION. CONTROL ROD DRIVE AND ORIFICING ASSEMBLY' REFURBISHMENT PROGRAM RADIOACTIVE WASTE HANDLING ANALYSIS 4 PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION PREPARED BY: A<deuc/r A. balSt-Frederick J.'iorst Support Services Manager / Radiation Protection Manager i i 3 i ~ ? N 4 e i .v.

i _m _;;_ --- ~o -FORT ST-VRAIN STATION 1 CONTROL ROD DRIVE AND ORIFICING ASSEMBLY REFURBISHMENT PROGRAM RADI0 ACTIVE WASTE HANDLING ANALYSIS Introduction -The radioactive waste generated as.a resultlof the Fort St. Vrain Control Rod Drive Refurbishment-Program will fall into two general-types: - relatively low activity, high volume waste such as-anticontamination.

clothing, gloves,

wipes, cleaning materials,. reserve shutdown material, and the like; and relatively high activity, low volume waste. including-the control rod 1 clevisJ bolts, cable and fittings, and control rod cables.

' The handling methods for each of the two waste types will differ and are described below. Low Activity, High Volume Waste For the most part,'this waste will be handled in accordance with-existing plant proce'dures' relative to collection, transport to -the on-site compacting building, compaction, and staging prior to shipment off-site for di;posal. At the _ current time, Fort St. Vrain does not have an approved low level waste disposal program satisfying IOCFR61 requirements. This was identified in NRC Inspection 83-28 as Open -Item 04 and is being tracked as Corrective Action Request (CAR) 84-005. by PSC. An; approved program will be in place prior.to shipment off-site for disposal. Currently the PSC Office of Executive Staff Assistant is evaluating via CAR 84-006 the Fort St. Vrain on-site waste staging facilities (NRC Inspection 83-28, Open Item 05).to determine an acceptable activity content for staging. At no time will the activity placed in the ' staging area exceed the acceptable quantity as determined in response to CAR 84-006. Reserve shutdown material will be handled on a case-by-case basis to ensure proper handling and staging techniques are followed. I ! [ 3

.High' Activity, Low Volume Waste In accordance with the Refurbishment Program, clevis bolts and cable endifittings will be removed from each : control rod' and pla'ced remotely ;in a Jshielded~ transfer. assembly in the Hot Service' Facility. The two clevis bolts and two cable ends - from-

l

-one.Erod ; pair . ill. comprise a full'. load for the transfer w assembly. The assembly will be removed 'from the Hot -Service Facility.with -the reactor building crane and moved to the northwest corner of the Refueling Floor. PSC has staged in this . area..two' shielded storage containers with approximately 6.2-inches of lead equivalent shielding which were designed and built by PSC~ to~ accomodate a Chem-Nuclear Systems 1-13G Cask Liner. A liner-will be placed in the shielded _ storage container, the clevis-bolts and _ cable ends will be dropped. remotely into the-liner, and the shielded lid for the ' container will be put into -place. In the event-that the liner becomes full prior _t'o completion of the Refurbishment Program,- _ a liner in the;second shielded storage container will be utilized. The liners will be removed from the containers, placed in 1-13G or equivalent ilicensed casks, and-shipped off-site for disposal following-completion cf the Refurbishment Program and development of an approved disposal program. At no time will the storage containers and liners be placed in the ' staging facility. Control rod' cable will be evaluated on a case-by-case basis, based on radiation levels, to determine whether the cable will be placed in the shielded ~ storage' container or the staging facility. _In any event, the cable will be cut into manageable lengths as it is removed from the control rod assembly. Conclusion All radioactive waste generated as a result of the Control Rod Drive and Orificing Assembly Refurbishment Program will either be placed in the on-site staging - facility. or remain on the Refueling Floor. No waste will be shipped for disposal until an approved waste disposal program is in place. The activity in the storage area will not exceed the L amount ~ contained in the evaluation being performed by the PSC Office of Executive Staff Assistant. ThroughL careful waste management techniques, radiation exposures will remain as low as reasonably achievable. 6 c-r ATTACHMENT 5 ~;TO P-85040 FORi ST..VRAIN STATION. CONTROL ROD DRIVE AND ORIFICING ASSEMBLY INTERIM-SURVEILLANCE PROGRAM 4 PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION i ~ // PREPARED BY: Charl'es'H. Fuller Station Manager f W i 6 L L .I l 1 I i l k g' t

': ~ - > m. i n FORT ST. VRAIN STATION -CONTROL ROD DRIVE AND ORIFICING ASSEMBLY INTERIM s

SURVEILLANCE PROGRAM i.

Weekly Surveillance f Objective -.0btain _ data.for analysis _ and long ' term trending; exercise .the rod; test' selected -circuitry;- verification of FSAR assumed escram time; confirm control rod operability. Methodology " Rod Drop" of approximately. 10" fori selecte'd. control rods. Elements of Tests for Fully Withdrawn Rods 1. Obtain analog and digital position.

2. ' Verify " Rod Out" light is~ lit, " Rod In" and." Slack-i Cable" lights are not lit.

I 3. Drop the rod approximately.10". 4. During the drop, obtain back EMF data. 5. Verify " Rod Out" light is not lit. f 6. Obtain analog and digital position. 7. Withdraw rod to full out position. 8. Verify " Rod Out" light is lit. 9. Obtain analog a..d digital position. i u s.L

F 2, .w l Elements of" Test for Partially Inserted Rod: '1. Obtain analog and digital position. 2. Verify " Rod Out", " Rod In", and " Slack Cable" lights are not -lit.' 3.' During the drop, obtain back EMF data. 4. Obtain analog and digital position. 5. Withdraw the rod _to its previous position. 6. Obtain analog and digital position.. Elements'of Test for Fully: Inserted Control Rods t 1. Obtain analog'and digital position. 2. Verify " Rod In" light on; verify " Rod Out" and " Slack Cable" lights off. Elements of the Test for all Control Rods 1. Obtain CRD motor temperatures. 2. Obtain purge flow if installation on. individual rods can be achieved prior to startup. 3. Verify that no " Slack Cable" lights are lit. Discussion The obtaining and comparison of analog and digital position indication confirms the satisfactory operation : of_ -the dssociated potentiometers. The acceptable deviation between the indication' will be 10" which is well within the deviation assumed -in the FSAR for different control rods within a group (2 + 1 foot per Page 3.6-19, Page 7.2-9, and Section.7.2.2.1). Deviations greater than 10": will be resolved by cnlibration if possible, or comparison with 1 operable position switch indication. If this is not successful appropriate corrective action will be taken to ensure compliance with Technical Specifications. A rod drop of approximately 10" is performed by deenergizing

the control rod brake for a specified time. This portion of the test confirms that the brake assembly is operating.

properly, and that deenergization _(such as during a, scram) will in fact result in brake release. ,---w--- ~ ,r

From-the distance dropped and the ' time of drop,- an approximately averaoe scram time can be calculated. Although. not-strictly representative of a full scram time (the rate of rod drop is position dependent), it is conservative for the near full out position because the rod is accelerating from rest. The acceptance criteria will be-160 seconds, which is the maximum scram time stated in the FSAR. -This calculation will provide an early indication to -the operator of control. rod operability, and can identify those control rods for which priority evaluation (e.g., back EMF) should be given. The control rod will be declared inoperable based on the distance and time rod drop data until more -sophisticated analyses or tests can show acceptable rod performance. Back EMF data will be obtained and analyzed to confirm that the control rod is operable to scram. The data will be compared with previous back EMF data. for detection of adverse trends which could result in inoperability. ~ Verification of " Rod Out" light indication confirms, on a weekly basis, that at least one of these two redundant switches is operable. The withdrawal of the control rod from the " dropped" position _ confirms proper brake release and motor operation upon withdrawal. Finally, withdrawing the rod to its full out position and obtaining the'" Rod Out" light confirms proper operation of the withdrawal circuitry ~ and the interlocks which deenergize the motor upon limit switch actuation. The obtaining of control drive motor temperature serves a two-fold purpose: (1) to ensure that the tmperatures do'not exceed the maximum allowable temperatures of 272*F and; (2) for-use in trend analysis and possible correlation with other data collected. In the event that any monitored motor temperature exceeds 272 F, appropriate corrective action will be taken to lower the temperatures below 272*F, or the rod will be declared-inoperable. Subsequent testing will be performed to confirm the rod is operable to scram. 'Soecific Exclusions The rod drop test will not be performed on the regulating rod. Such testing could ' result in an unacceptable transient. AwM ~ s - Rod drop tests will not be performed en control rods whose - testing acould result in-automatic actuation of-Plant-Protection -System functions such as RWP and scram. Plant conditions at the time of the test will be evaluated to make such determinations. It is not expected that this exclusion will result.in frequent exemptions.- Rod ' drop tests will not be performed on control rods whose testing would result' in a violation of. the Technical Specifications. 1 d 4 e e J e 6 <U i i j

.m ^ ;_ ' s v ~ I W. Quarterly Surveillance Objective - To supplement information obtained on the weekly surveillance; to verify ' redundancy. of-selected ' control-rod position limit switches. Methodology - Chsck redundancy. Elements of Test for Fully Withdrawn Rods 1. Determine which of the two redundant " Rod Out" limit switches has actuated. 2. Bypass this switch to allow further rod withdrawal. 3. Withdraw the rod further until the second. switch. actuates. 4. Confirm operation of rod motor deenergization interlock with second switch actuation. l 5. Return rod to original position and remove bypass. i Elements of Test for partially Inserted Rods 4 Not Applicable - Partially inserted rods will'not have " Rod In", " Rod Out", or " Slack Cable" lights lit. - Weekly surveillance will compare analog and digital indication. Elements of Test for Fully Inserted Rods Not Applicable - Technical Specifications prohibit the~ l withdrawal of these control rods out of sequence. Such withdrawal would be necessary to confirm limit switch redundancy. The weekly surveillance will compare analog and digital indication, and that the control rod " Rod In" light is lit. Fully inserted rods are already performing -their design function. 4 D + F.

7 Mem'~ - Refueling ~Shtudown Surveillance Objective - Same' objective. as for the weekly and. quarterly surveillance, except data will be obtained over the full scram distance. Elements of the Test

1.. Determine which of. the two redundant " Rod In" limit switches has actJated. Jumper this switch out.

2. Withdraw the rod approximately 6" and re-insert to. actuate the second " Rod In" limit switch.

3.. Confirm operation of the ' rod motor deenergization '

Anterlock with the second switch actuation. 4. Withdraw the rod to the full out position. 5. Confirm " Rod Out" limit switch redundancy. 6. Scram the control rod. 7. During the scram obtain back EMF data and total scram time. 8. During the test, compare analog and digital position indication. l r

, :sc l' ATTACHMENT 6 TO P-85040 s \\;- WATTMETER USE TO DETERMINE INSERTED ABSORBER STRING POSITION Prepared by: Jilli Eggebroten Technical Services Engineering Supervisor Approved by: Fran L 'J. Novachek' Technical / Administrative Services Manager Public Service Company of Colorado Fort St.- Vrain Unit #1 b %.) 0 0

'~ .L ur , n;4 l ^ ri x; .w o ~ 2' I. ABSTRACT- 'A' wattmeter has been used on two occasions tol determine "in". rod position and on many other' occasions.in -the recent.past to establish -conditions such as freedom of motion, Thigh _ loads,-or 'other abnormal parameters.' A-request was made in the near-past-4 toojustify the-basis. for this test;' the following document provides a sound technical; basis for the use of this test. g II. BACKGROUND When a control: rod-'is shimmed in either direction, the drive i.~ . motor is activated which in turn raises or lowers the absorber . pair via a gear train and wire. rope riding over-a drum and guide - pulleys to the absorber pair _itself. Normal mechanical --losses

(bearing,.' gear, pulleys, seal, etc.) in. addition to absorber weight represent a load on the motor against which work must be done when the. rod pair is raised. In: addition, I2R losses in -

~ 3 j -the motor represent a regular electrical loss. 'The result of these-is that movement of a control' rod pair in either direction .causes distinctive transients which, to a knowledgable observer, contains. a multitude of information that.goes far beyond the provided instrumentation (motor cverload trip, etc.) and can be used 'in unusual circumstances to establish -~ condition and location (in some specific cases) of the absorber pair. III. DESCRIPTION - TRANSIENTS IN/ CUT A. typical shim wattage transient always includes '(in and out)= a . jump in wattage to_ a -peak as the mechanism accelerates, a reduction to an approximately steady value in 5-10 seconds, and e a steady (but slowly varying) wattage for the shim -duration as- 'the cable winds or unwinds on-the' drum sheave. The' shim always -terminates with a decay in wattage to.a.zero baseline.in 5-10 l seconds. l n.

- ~ ' se l'

p { e sreet i. ~ i

sm q es

,,, ~, ,.-_s .. ~ -. ,.. _ -.,,. _. ~., - _...

n., .,.-___,.c x-s t' It s W 3' i The, theory - for this :behsvior tis as follows: the shim motor consists of a' 4 pole, 3 phase induction. motor.- A capacitor bank-is paralleled across the motor winding' phases, but.has no effect on torque when the unitlis driven ' from - the AC power supply, since~ the ? bank's-'only effect is:to change power factors. An ~ induction motor develops' torque by the principle of rotor.. slip; it is assumed that the reader is familiar with this idea. The . greater the slip,-the.. larger:the induced fields on.-the rotor, -the larger-.the tor'que, and-the larger.the electrical load. Wattage will-increase rapidly'for.a; freely-moving mechanism as -the transient'begins, and the rotor and mechanism acclerate. As the driving torque is developed, -the rotor approaches -steady = speed (corresponding to some steady slip value), and the wattage ' declines to a steady value, eceieheton. o.r .%f y ( d / cec) - met : Note that, for no load on the motor-(i.e.; such as during a bench test), a positive power consumption results due' to 'I2R-losses in.the stator windings and bearing friction, which should r -be the same in either direction, i.e.; p CW OCW t C1 oi t Cr<c) j_ f This is a useful reference _ item for the 'following discussion. i-For an outwardishim, the opposing weight of the rod pair causes more slip ~due to the greater rotor load. Hence the rotor-stator l field interaction-is greater, greater current demand on'the-stator occurs, and a higher motor load,results. - For 'an inward ' shim, the assisting weight of the rod pair causes ~ less slip, ' tending to drive-the~ rod' in. '(Note;that the t - directioni is reversed.) In this case, a reduction in the field-interacti_on' occurs, and less motor -inad. results (or i equivalently, the. operating' point is closer to the synchronous L speed).. 6 4 ~ ,,,--.,,v. 7 m,.-...w.m,,,.,.,w.- ~,. - -,

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'-+,- m -.w w 3 m g_ _ - _ I n 4' m 4 ' t i . Note!. that. if' the' motor could be driven externally at exactly synchronous (stator) field speed, n_o. load would result, and -.any 2, power consumption 1 would: represent : only the 18R losses of the stator field. 5 h Also ' note'.)that._ physically, ' one ; expects a higher load for an outward shim, when the motor must do work against -gravity in-i addition to its own internal losses, than an inward shim, where i work is actually done' on the motor. Note also that-for an inward shim, again, the mechanise inertia e means that instantaneously after the start : of the. shim, the e rotor' fields are moving slower than the stator fields. -In this case, however, both'the gravity torque and the developed torque assist:.to-accelerate the rotor in the "in" direction, so that' the transient' duration is shorter (1.e.;:the "in" shims tend-to l be more sharply peaked than the "out" ones), t ~ ~I70 4 P isen cut l' exas j av k. C I a t t - Ore) . p,gqq. M smM6 i w ,4 L i 1

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j; [ Any sort of impeded mechanism motion shows up as extreme' changes in power consumption due to the dramatic' slip ' changes.that occur. To some' extent, elasticity of the wire rope'm_ar mitigate a { these -however, they are still'obv1ous should any sudden rod pair motions occur. l j doow p l NW ( l i ceisert ' t(see)' O t' .w-1 +e e =n-+

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% -e V,- s a e,vv-.<-+e*%. -4 -e%>w. t es fm rw,=.,e-+-w t+- -~, s y g e ygr -v +-

ym. 5 Superimposing _ _th.e. wat.tage traces for.an "._ou.t_" a_n,d "._in__"_ shim we P gg 4y IMort as the) Average of nominal in/out steady values; 90 +'46 = 136 watts or 68 watts. 2 T The work done raising the control rods, neglecting 18R losses, and neglecting any frictional load (from viscous drag on the absorber pair, drag in the graphite / guide tube channels, and gear train losses), should be less than 90 watts. The following check, assuming no frictional loss in the mechanism confirms this. Nominal' speed 1.05 in/sec ( 190 in ) 180 sec P = FV (Physics) Where F = weight of 2 rods = 240 lbf and V = 1.05 in/sec P = (240 lbf) 1.05 in/see 1 ft 12 In = 21.0 lbf ft/see 1.3558 watt Ibf ft/sec = 28.5 watts 29 = 61 watts represent the nominal electrical and Hence 90 mechanical losses in the system. For a mechanical transmission' efficiency of90%permesh,andamotorefficiencyof80%(both nominal values for similar equipment),- the expected out shim power would be 28.5 watts 0.8 (0.9)* = 54.3 watts. This compares with an observed range of steady values varying from 80 to 110 watts from all testing, for outward shims.

w_

t. _

s n. ...t -{. 4 i i 6-Finally,e' note :that 'over.a 190 inch rod. pull (insertion), the '~ cable, drum will wind (unwind),1 starting from (ending -at).the; 7, ' fully-inserted position...At this position, the cable drum is completely unwound, i.e.; the rod pair hangs free from'the: anchor' pins. _, p_ j paa. =_ ,e, o i a s + min) Instantaneously a shim,.since the' drum is not wound, does no . work against the rod pair weight; 1.e., until the ' drum. reaches one quarter turn, the motor is not working fully against the weight of the rods, L as the ~ moment load has not completely -i developed. The distance travelled by the rods is' ~ 2,(6 in) = 9.42 inches, and d= C = 23r = T 4 4 t = 9.42 inches = 9 seconds. 1.05 in/sec g The-actual moment load increase functional form is probably a j sine-type relation, based on drum rotation. For the last 5 seconds on an "in" shim, or the.first 5 seconds-on an "out" shim, a change in the steady wattage value should be seen; this is the observation. All "in" shims terminate with the following: } P g l f. 4d.o a 3 g svs. 1s Note that.normally, as the full "in" position is reached, the l power to the motor is cut off as the "in" limit' switch..is L activated. i l l w

. q__ 7 i An "out". shim is not so simple, as the initial peak transient must occur. Nonetheless, the same behavior is observed.here. The transient peak decays to a value below the steady value and then recovers-p Ishu - M ** e4 a -f & c-to m. + These transient characteristics are unique to the fully inserted position. Many r3rmal rod shim wattage traces have been reviewed and the pattern is entirely consistent. Finally, note that the direction of drum rotation is irrelevant. If the motor could be driven in beyond the "in" limit switch cutoff position, the rod pair would be raised as the mechanism wound around the drum in the reverse direction. In this case, an "in" shim transient should appear as an "out", and vice versa. It is on these observations that the wattage verification of rod positionincorporatedinTSP-30(proposed)isbased. IV. TSP-30 LOGIC Objectives First, sne test must verify freedom of rod motion. Second, it must establish position for rods as being in (not just cam drum or equivalent pulley position). Third, it should establish that both rods are supported on the mechanism, if possible (actually, this is only " nice to have"). The wattage test establishes freedom of gear train motion obviously; impeded motion or locked rotor conditions are easy to identify. Rod motion is determined by observing correct nominal values for in/out shims, with the magnitude of the out wattage in excess of 78 watts, (if, in fact, both strings are supported). A steady value of less than 68 watts should be taken as evidence that one rod is not supported, particularly in conjunction with slack cable indication.

,r m T ~ r 18 s. j 1 - Backcround-s i ~ TSP-30, Evaluation of Shim Motor Wattage Characteristics, is, the culmination of an extensive review 'of 'all applications.of: wattmeter testing' performed'in the past,- particularly that done under T-214, Wattmeter Testing. As 4 a ~ result. of. an intense examination,.'a number.of. clarifications and conclusions can be made. 1 Refer _to Attachments 1-4. These represent a summary of ~ measurements of data on shim transients collected under T-214 in two general' time periods., The first. was. post-third refueling, from about. March 11, 1984-to 1: -April 15,~ 1984; the second was post. June 23, 1984 i Failure-to-scram

Event,

' collected-June 23, 1984 to June 25, 1984. There remains additional data collected. [ from July '1,.1984 through November 1,'1984 which was taken - - on mechanisms in the Hot Service Facility, primarily, and i has not been extensively evaluated. It appears, from' i. preliminary ' review, to be completely consistent with the other data, 'very similar to that collected' in the March 11, 1984'-to April 15, 1984' time period. Results ll Evaluation of the data revealed the following qualitative j and quantitative results. 4 I' 1. Normal in/out shims always start with transient l peaks occurring over a range from 140 to 200 watts. These decay to a steady value. over 'about 2-4 l divisions on the strip chart, where -.each division j is about 2.5 seconds long.. 2. "Out" shim transient peaks 'are higher than "in" shim ones, being about 160-190' watts versus 144-160 watts'for "in"-shim peaks. On any given CRDOA shim . motor, these peaks are distinctive, with a: nominal l 16-24 watt difference.. i 3. The rate of decay of "in" shim transient peaks is l similar to that of "out" shim peaks, with the i exception of the first outward shim from the [ inserted position.; i ( 4. For a continuous shim in the "out" direction from 0-l' to 192 inches, a very slight wattage increase. is seen, of about 6 watts; the nominal steady wattage observed is 90 watts with a range-of-80 to-110-watts observed. -e 3 -ve-,-.- r- .~s-, ,,-evi,- +w w,-w,gy y ,.v-t-- .+w,,.,--,--+,,,-~is.-- i ww--- t.-%-,.qviv 1 - r v, v--9., .3-,,,, - -,,.v,www-r-p--p-w,-, --r y r-pww --p-my

~.. + 1 9 5.- For~ a. continuous shim in.the "in" direction from ~192 to 0 Linches,~ a very slight wattage decrease is-observed, of? about 6 Lwatts; : the nominal steady wattage observed.is 46 watts, with a range of 30-64 watts observed. 6. An "out" shim transient startingL at..the-fully ~ inserted position is distinctly different ~ from any. other "out"': shim transient. Two aspects of the transient are different - the peak wattage' value and thel rate of decay. In almost all cases the rate of the transient decay'is so much faster that-a pronounced " dip" -in' wattage below.the final steady-state value is observed, due to the' winding of the drum sheave phenomena;lin every case, the decay to the steady value is significantly.--faster. 7. An '"in" shim transient terminating at the fully inserted position exhibits a -distinct., rise in steady wattage value as the drum sheave unwraps not. observed at any.other location, 8. Even on mechanisms with poor wattmeter traces, the above behavior is distinct ~from' other transients since the results can be repeated-(i.e... spontaneous variations in'the wattage record of a poor rod are not duplicatable). 9. A mechanism with only-one absorber pair supported will have an "out" steady wattage 'of aboutL 60 watts, based on Instrumented. Control Rod Drive (ICRD) data. 10. Rotor seizure - or other erratic mechanism behavior is indicated by erratic wattage recordings exhibiting sudden variations in wattage. while shimming. 11. A periodic oscillation of about 4' watts magnitude is cormonly seen on "in" shims. This has. no significance with regard to mechanism performance.- 12. Variations in voltage at the MCC can have a significant effect on the level' of all values observed. For effective test' results, voltages should be at 105 nominal phase-to ground RMS volts.

. p. Q.-. ~ 10 13. Although 'T-214 did not have provision for voltage u measurement and control, cursory _ examination :of .i applied voltage during drive, performed under T-227- .I periodica11,v, indicated the nominal phase-to ground RMS voltage-to be close to 105 volts. ~However, the -failure te monitor and record voltage during test-presents a significant; limitation to data interpretation,' except

where results are

" normalized". 14. When driving the. mechanism in beyond the "in" limit, a change in transient behavior. does occur; continued shimming in-the "in" direction exhibits characteristics of an "out". shim, while shimming out exhibits characteristics of an."in" shim (while the mechanism is still beyond the normal position.). inserted Operations and Maintenance (0&M) Manual and FSAR References to shim motor wattage are made in the O&M Manual and FSAR, as indicated on Attachments 14 and 15. No - steady wattage outside the 80-110 watts for outward shims'of normal rods has been observed, although that-referenced by the O&M Manual is 72 watts. This might be consistent with references to an 18 watt increase being required to cause failure to scram, although there is another reference to 60 watts as the= value at which failure to scram is possible (steady out wattage), at 105 volts, which is clearly inconsistent. Operational measurements, indicate'd nominal values of 90 watts, with the lowest values'being 80 watts en a normally. configured CRDOA. It must be emphasized that all measurements collected were done without voltage monitoring or control, hence were' subject to wide variation. The FSAR also references 72 watts for normal outward shims, and 90 watts as the steady outward shim wattage 'beyond which scram capability cannot be. assured. The manner in which a wattage device is hooked up can affect the output. The Fort St. Vrain devices have been carefully checked to verify' that-they are correctly installed and providing correct output values. ~ e i l w

- - 33 + mw ~ = Oy w m y o ,[f g [ ' - _ kbh, _ c 11'- r i j l

Procedure Logic" 1 Technical Servicesi Procedure (TSP-30)Lallows measurement-

~

of wattage forl monitoring purposes, as done in.the -past,

~. with a clear guide-for, interpreting the'results.- t This can be used to establish freedom of motion,=. estimate.' position-ifrom at known. position, _ and. verify cable weight. These ~ functions ~ are useful for monitoringHpurposes; during -maintenance, ' trending, and monitoring performance in the PCRV under-various operating conditions. With regard to rod'"in" position verification, TSP-30 uses; a three-step approach which starts with the mosti easily .identiftable -(and obtainable)- _ indication of' -rod full-insertion, progressing _ to a' second 'more detailed evaluation -if 'the - requirements:for.the first evaluation are not met, and-proceeds to a fin'al, definitive test?and . evaluation if the first two simpler evaluations cannot meet the test. basis requirements.

Each ' step' involves

~ repeated ' step performance so thatl postulated data collection irregularities should have--'an.almost -trivial chance of. affecting the conclusion. Note that'in the: volumes.of data reviewed, no data has been ' observed that would indicate invalidation of these-tests. Because of the repetition requirements, it_ is possible that' a given test -performance would not;-meet the: requirements for concluding the rod pair was _ inserted,- even though a preponderance of data indicated that it was. Failure-to reach the requirements for certifying' insertion does not mean that the rod is not.. inserted.. or that: additional -testing may not' be done. In fact.1the best approach to the test would be,to perform the test,-~and if there was very marginal indication of insertion based on that step approach, continue ~ on to the next, stronger version of-the-test. (If the results looked very good except that one data point'was not distinct,irepetition of that step should allow conclusive results). Two-major points should be made with regard to criticism voiced on these tests in the past. First, the acceptance - criteria are now ' spelled out formally in terms.'of numerical values and guidelines' based on data collected under T-214 on all CRDOAs. There are margins included here that in many instances would invalidate position conclusion from data runs on rods that were known inserted -at the time of collection (under T-214). Most data runs would however, allow the correct conclusion: without -l repetition.of that test' :tep'. Secondly,.each test sequence repeats the sequence.- i l

T '12; i This ' provides additional assurance that electrical system-variations will not yield any transient which could be incorrectly taken. to indicate _ inserted, condition. In addition, note that all results are normalized, and absolute levels not used for acceptance criteria, again minimizing any effectslof electrical system variations. For 'the scrammed condition, for freely-running rod pairs, the' rods will be bottomed out. Each test sequence starts from this condition (scrammed), so that presumably the 1 rods,are bottomed. The ' first. test approach merely shims the rod _ pair "out", then "in", repeating twice, and looks for.the dip in wattage'on the "out" shim (after the peak) and the rise in wattage at the end of the "in" shim. LIf these location indicators are observed (within the numerical limits specified), the rods are considered "in". This second test is based on results observed consistently under depressurized/ cooled-down conditions'seen in T-214. Its one weakness is that the initial dip is not quite so pronounced under - other conditions, so that the requirements might not be met.if the test were desired to be used under other conditions. Hence the second test. This test consists of evaluating the inserted condition again based on shimming "out" from the "in" position, but using the combination of wattage peaks and decay times to discern the difference between the first "out" shim and the subsequent "out" shim characteristics in the sequence of three shims. - Again, these two aspects of behavior are easy to discern, and the test, although more complicated to evaluate, is still straightforward with respect to data collection. The possibility occurs, however, that the results will not allow a definite conclusion due to data spread, poor test conditions, or otherwise. r G

. sw.n. 7;v;m;w w a - + x. n. m:, a ; ;;--

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+ e J L ~ w, .x 93- + .g y '13: j .g 3 j . ;;b. j g-3. is the worst to I The J finalf: test, and :most definitive,~ certainly 1 break i actually. perform because it will almost (. thef multijaws coupling,- hence should.only be used on a'- ~ damaged mechanise with a damaged-'multijaws coupling ~.(no analog / digital sindication or? inconsistent ^tndication, i 1 compared to in/out limit' switches),7 with no;;"in" - 11mi t' ~

s u indication.

This test involves scramming to establish A 2 "in"E position-' (presumably), ~and then performing an- "out"/"in" : shim pair, which should approximately return the' rod' pair to its original "in" position,- to establish _ i. ll, (reforence -shim values,' for normal shins..An "in"/"out" ~ i i sequence is then performed,.which should Edrive -theo drum i j. ' sheave -beyond its'. normal-limit, raising the rod. pair on the ~ drum in: the reverse : direction. Hence the. l characteristic is reversed., The "in" shim is actually L lifting the rod pair, while the "out" shin is loweringLit. L By observing this'. reversal,"in" shim behavior,.which is. i. easily discernable!so long as the drum' wraps to a 7 quarter-1 j turn -(to develop the moment arm, where the wattage values i j are nominally 90 watts to raise and 44 -watts to lower), l' the rod. pair ' position'is absolutely determined._ Again,: the sequence is repeated to confirm the behavior. i ( r Final _1y, the ' question of 'the condition of the absorber pair, supported or not,:can be' addressed in--part using data collected from an ICR0 (only one supported rod). The ~ i nominal wattage observed here was 60 watts for 'an _"out"- i shim, compared to 90' watts-for a normally configured rod (range 80-110 watts for "out" shims). This~ suggests a' c: T limit of between 60 and 80 watts to determine the normal f I condition with both' strings supported. In conjunction with trending, any sudden ~. reduction in nominal steady. "out" wattage could probably be used to confirm slack i j cable indication. A review of'the slack cable shimming on J Region-7.CRDOA'5N 25 done July.20, 1984 indicated a-steady' i wattage value ~of 76 watts (the same CRD0A," SN 25,- exhibited 88 watts. on March 13,.1984' and' 86 watts on June 25, 1984 for nominal out shim steady wattage), while installed in Region 14). -e t l l l l i -} ~ i l e

%.a .w 14 V.. CONCLUSION The.;CRDOA wattage test is. viable for monitoring motor, train, and rod condition, can extract substantial information under a variety of conditions, and can be used to establish rod pair -iriserted position. Additional testing should be done under more . controlled. conditions to confirm results obtained thus far'and ^ determine data spreads. Trending of this information' should continue to monitor performance. Apparent discrepancies between FSV data and the FSAR and O&M Manual should be resolved and corrected. Examination of a digital or other wattrecording device to increase the sensitivity of the measurements should 'be considered, although may not be necessary if voltage variation is found to-be the factor limiting test sensitivity. The test is entirely normalized with respect to test values so that absolute levels are not important. Attachments 1-15 w

1w. ~ - -.. 15 List of Attachments 1. Control Rod Drive and Orificing Assembly Installed in PCRV, rod pair inserted 2. Control Rod Drive Mechanism Shim motor / brake assembly Gear train Cable drum Guide pulleys Slack cable assembly Indication pots / switches 3. Shim Motor / Brake Assembly Wattmeter Chart Data Two general time periods for data collection occurred: Data I - March 11, 1984 - April 10, 1984 Data II - June 23, 1984 - June 25, 1984 All following references to I and II refer to two sets of wattmeter data, each generally consisting of summary data for each of 37 CRDOAs (as available) in the indicated Region. 4. Out Shims Data I 5. Out Shims Data II Summaries of key data values for CRDOAs for outward shim data 6. Out Shims Analysis I 7. Out Shims Analysis II Summaries of key differences used to support position verification by out shim data. 8. In Shims Data /Analyris 1 9. In Shims Data / Analysis !! Summaries of key differences used to support position verification by in shim data

10. In Shims Transient Decay Time Analysis II Summaries of decay time data for comparison against "out" decay timos

y v - _ = - - - - - - ~ 16 4 ~ ~11.= Individual CRDOA Shim 3equence Variation Analysis i i Detailed Analysis of--discrete values on ten individual CRDOA strip charts.that' identifies-the variation 'that occurs in. key parameters used in the test.

12. Explanation of Wattage Test Evaluation supporting data, items j'

. 4-11 above. L '13. TECHNICAL' SERVICES ' PROCEDURE ' NO. 30,' EVALUATION OF SHIM MOTOR WATTAGE CHARACTERISTICS (PROPOSED)

14. D&M Manual Wattage _ References

15. FSAR Wattage References t

I i i l I I i l I t s

L- ~ I i + y f.,\\ REFUELING PENETRATION c );h[ CONTROL ROD /. DRIVE MECHANISM / 9 R ADIATION SHIELD ~ ORIFICE CONTROL ' i. MECHANISM 8 LOW CONTROL ORIFICE l CONTROLROD d$f_I WITHDRAWN I - ? I 1 m 4 1 Ii l ,u l 'I i i CONTROL ROD INSERTED l i l du u f=k,- i t i l t \\ l CONTROL ROD DRIVE AND ORIFICE ASSEMBLY i

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^ s / - ARMATURE f F ROTOR SHAFT / PLATE C s x e a [R ' /,W,' s -) / '7 l g j -*,( g .x.A.%j j t / a, w s 1% 4 s l j ' 1p% r z, ^x j 'N'd - fN a i = g I e//n 7iv,, -3 CENTER DISK MOTOR AND BRAKE ASSEMBLY i i I i j I

I cri e i-j: [. ./ j Page 1, ' T;; ATTACHMENT 4 'i ,7 OUT SHIMS DATA I 1 l NOMINAL l@ANSl[N1_fLAKS l I 'FIRST-l S T E ADY.' INillAL -1 NOMINAL. ]. lNil l AL. l NOMINAL l HINIMUM i VALUE - VALUE l-VALUE-I DECAY-1. DECAY l DATE . REcloN (SN). (X2 WATT) l (X2 WATT) (X2 WATT).-l (X2 WAIT) l TlHE I .T I ME. 'l I I I l-1. I l-l- I. l I r 03/11/84 l '1(24) l 38 I 44 80 86 ~. . 0. 7

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I 03/11/84 l 1(24). 38 43 80 85.

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1.5J it-l '03/11/84 1(24) 39 - 42 1 80 0.2 ~--- l l 03/11/84 1(24) 38 48 8 80 <l. 0.2 ~ 'l 03/11/64 1(24) i 3T 43 1 77 1.2 'l I~ 03/11/84' 1(24) i 38 42 Il 77 l 0.8 l _l' '03/11/84. 1(24) 37 44 il 78-1: 0.8 Lt. I H I i 1 Moan: 37.86 43.71 78.86 85.5-1 l' 'l 2( 3 ) '- 56 56 82 92 1.0 1 3.5 1 l -03/23/84 3(31) 1 50 51 80-90 1.0'- 1 3.0 03/28/84 4(31) i 46 50 11 80-85 l 1.2 1' '.3. 0 03/13/84 5(10)l 34 40 ll 80 85, 1 0.7 l' 1.5 03/13/84. 6(29) 37 44 80 89-1 ~ 0.7 l-2.0 7(18) 39 42 80 86 i 0.7 -l

1. 5.

- 03/28/84 8(38) 47 50 82 90' i 1.2 l 1.5' 03/28/84J 9(26) 50 52 84 95 0.8 1 2.7 03/28/84'.. 10(14) 43 50 1-84 95 1.5 1.9 03/28/84 l 11(30) 47 50 1 83-95 1.2 2.0 -04/09/84 'I. 12(36) 52 1 54 I 83 90 0.8 - 2.5 1 04/09/84 13(16) 47-50; I: 80 87-l- 1.6-2.5 -03/13/84' 14(25) 36 44. 80 - 89' 1.0

1. 7 -

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19(13), 47 I 50 85 90.- 1.3

1. 9 -

'04/09/84 20(32). 42, 50 81 90 1.0 2.1 50 1 82 1 90 04/09/84.. 21(28)' 46 50 1 78 88 1.2 2.0 1 2.0 04/09/84 -22(5) 47-50 l 85~ 91 1.4. ~ 04/09/84. I i. ll ~

1. 6 -

23(39). -- Data Not Available. ~

No mean o r s tanda rd da ta.

' Notes:

1. Units or time are in divisions or the strip chart.

2.' Wattage. values were determined on a 0 - 500 scale where the maximum dorloction corresponded to 1000 Watt, hence all values should be multiplied by 2.0. ~ I, 4 ~. i

~. b _l'1 Page 2, ATTACHMENT 4 DUT SHIMS DATA 1 ~ NOMINAL -l: IRANSliMT PEAKS l' FIRST SIEADY -- l INiilAL

l. NOMINAL l -INillAL-NOMINAL. -l

'DATE REGION (SN) MINIMUM VALUE-VALUE l' -VALUE 1. OECAY DECAY ~ l- '(X2 WATT)' .(X2 WATT) (X2 WATT) (X2 WATT) 1; ' TIME T I ME -- 1 3 I 04/10/84 ' 24(23). 48 54 89

1. 2 -

2.0 l 4 l 04/10/84'-l 25(7) 45 54 82-90. 1.1 1.3 1.? 04/10/84~ 26(1)- 46: 50 83 90L .1.6 '1.7, ~l' '04/10/84' 27(2) 45 53 1 81 1 90 1.2 -l-2.0 'l' - 28(44)- 481 48 74 i '80 1.1

1. 5 -

.I l 29(35) 43-47 83-89 1.2 1.4 ~I ',8 30(11) 43 43 1 77 87 -0.7. 1.1 l 31(17) 40 45. 79 87 1.2

1. 4,

32(15) 37 1 45. -80 88 0.9 1.3 33(34) I _42 46 81 .88 1.3 1.3 1 34(22) 37 45 eo I 86 1 0.9

1. 4.

l ' l-35(21) 38 45 'l 80 l 86 ' 1. 0.8' ~1.4 ' l-l 36(8) No t pe rfo rmed due. to mo to r ra i lure. l 'l l I I 84 94 - I-

1. 2 -

2.0 37(4)~ So l-54 .-04/10/84' i 1 l l Mean: 43.48 I 48.41 I 80.85 88.71 .I Sta nda rd: 5.13 'l 3.87 l 2.32. 3.14 ~

I I

I l l l 1 J P i ~ a-Data Not Available.

No mean or-standard da ta.

Notes: :1. Units of time are in.illvisions or the strip chart. p

2. Wattage values were determined on a O'- 500 scale whero ~ the maximum deflection corresponded to 1000 Watt, hence all values should be multiplied by 2.0.

3 ? I

t

L l

Page 1 ATTACHMENT 5 l-Oui SHIMS DATA li } l l-NOMINAL 1RANSILNT P[AKS l t I rlRST l STEA0Y IHlilAL i NOMINAL.

INITIAL, NOMINAL i i.

~ DATE l RE010N (SN) HINIMUM i VALUE VALUE I' VALUE DECAY. DECAY l' 1 l (X2 WATT) (X2 WATT) (X2 WATT) (X2 WATT) IBMED TIME l .c I 1 -l 1 I 1 06/25/84 l 1(6)- 42 45 74 82 1.0. I -3.5 'I 06/23/84 2(3) l 48 53 80 95 l 1.6 3.0 1 06/23/84 3(37) 47-49 75 82 1.4-4.0 .l_ + 06/23/84 4(31) 43 47 74 87 1.5-4.0 l' 06/25/84 5(10) 40 42 74 80 1.5 4.0- 't. --06/25/84' ~6(29) 44 46 74 84 1.0 4.0 06/25/84 7 ( 18 ).. l' 407 45 l 71 1 80 1.3 4.0-06/23/84 8(38) 42' 45 74 88 1.6 4.0 06/23/84 9(26)- 50 50 83 88 ' 3.0 - 06/23/84 1 10(14) 46 48 80 88. 1.6-3.0 -06/23/84 l 11(30) 44 45-77 84 2.0 3.5 'l 12(42) 47 50 80 87 l 1.3

2. 5.

06/23/84. l. 13(16) l 43 44 75 81 1. 1.7 4.0 06/25/84-1 14(25). 42 43 72 81 1 1.1 l4.0 06/25/84 ' 15(12) 47 48 75. I 81 0.9- - 1 2.5 '06/23/84 16(33) 47 49 77 I 84 0.9 l 2.7: 06/25/84 17(41). 4T 49 il 75. 85

1. 4.

I

5. 0.

1.1 1 4.0. 06/25/841 18(40) 46 48 l 73 83: I l 06/23/84 19(13) 44 45 1 73 75-4.0 06/23/84 20(32) 43 45 1 77 87 1.4 4.0. 06/23/84 21(28)- 48 49-l 78 88 1.3 3.4 06/23/84 22(5)' I 42 45 75 82 1.6-3.0 06/23/84 23(39) 41 44 77 85 l

1. 3.

3.0 52' 52-77 87 l 1.5 I 06/23/84 '24(23) ' 49 49. '77 89. 'l 1.3 1, 2.3 06/23/84 25(7) 06/23/84 l 26(1) 48 50 80 90 .2.0 . I 3.0 06/23/84 'l 27(2) 46 47 78 85-1.3 l 4.0 l' 06/25/84 -l 28(44) 'l-43 45 72 81 1.0 1 3.0 1 06/25/84 29(35) -47 48 1 77 85 1.4 l' 3.5 1 06/25/84 30(11) 42 43 74 81 1.0 I .3.5 06/25/84 31(17)

44' 45'

'74 82 1.2 ' 3.6 06/25/84 32(15) 46 46 76 84 2.5 4.5. 06/23/84 .33(34) 44 44 74' 84 1.2-2.8 I il q; -- Da ta No t Ava i l ab l e.

No mean or standa rd da ta.

Notes:

1. ' Units of time are in divisions of the strip chart.

- 2. Wattage values were determined on a 0 - 500 scale.where the maximum deflection corresponded to '1000 Watt, hence all values should be multiplied by 2.0. a

1 p

i W

I. t: 'Page 2-ATTACHMENT 5 OUT SHIMS DATA II l l NOMINAL TRAUSIENT PEALS I ~ t rlRST STEADY INiilAL NOMINAL INiilAL MOMINAL l .DATE I REGION (SN) MINIHUM VALUE-. VALUE VALUE . DECAY DECAY-l l (X2 WATT) (X2 WATT) i ,(X2 WATT) (X2 WATT) . TIME ,TlHE I i 1 1 34(22)- 43-44' 75 82 1.0 2.0 t 06/25/84 1 35(21) 42 1 45 72 al' 1.1 2;3' t 06/25/84 1 36(8) 42 l 45 74. I 83 1.3 3.5 7 1 06/23/84 37(4) 44 48 78. l 89 1.5 2.3 1 1 ' 84.32 1. l Hean: 44.73 46.62 75.70

l 1

l ll-l. I Standa rd: 2.87 2.62 2.70 3.71 ,Y ~ ,j ' 1 ? $Y d - i3 1. f1 L-j Ti .7 l4 N:i x -- Data Not Ava i lable. ~

No mean or standa rd data.

Notes: 1.. Units of - time a re in divisions of the strip chart.

2. Wattage values were determined on's 0 - 500 scale where the maximum deflection corresponded. to 1000 Watt, hence all values should be multiplied by 2.0.

i. .E .I. J / N.

' sr '.h~ : a.. :

w..

i Page Ic . ATTACitMENT 4 c, PUT SHIMS ANALYSIS I -l DIFIERENCE, NOMINAL l OlFIERENCE, NOM I NAL - -DlFIEHENCE, NOMINAL i. I DATE REGION (SN) AVEHAGE - FIRSI MIN l -PEAK - FIRST PEAK DECAY - FIRST DECAY l .l (X2 WATT) l (%); I (X2 WATT) (%) - ( T I ME ) c-( 7,), I l ~ l .14 6 7 0.8. ..53 1(28) 1 6 4 1( 2rs 5 12 5 6 1.1-73 Li 1(24) ) 3 7 ll I 03/11/84 03/11/84 1(24) 10 21 -Il l 1 03/11/888 1(24) 6 14 l .I .I. 03/11/8fs 1 ( 2 84 ) 4 1 10 l I~ l. 03/11/84 1( 21s) 7 16 I I Mean: 5.86 13.43 5.5 6.50 'I 2(3) O. 0 to l 11 2.5 ' i 71 103/23/84 3(37) 1 2; i 10 I; '11 -2.0 67 03/28/884 4(31) 4 8 5 6-1.8 60 1 03/13/88 I 5(10) 6 15 5 6 1 0.8 53 1 03/13/8ts I 6(29) 7 16 9 10 ' 1.3 65

8. --------

7(18) 3 7 1 6 7 0.8-53 03/28/84 8(38) 3 6 l 8 I 9 0.3-20 9(26 2 4 l 11 12 4 1.9 70 10( Its ) 03/28/884 ) 7, 1 88 1 11 121 0.4 21 03/28/84 -03/28/84 11(30). 3 6 l -12 13, 1-0.8- .I 14 0. I 'e Ofs/09/84 l 12(36) 1 2 4. 7 I 8 1.7 l 68, W

z

.04/09/84 13(16)- 3 6 7-8 0.9 36 -l a 03/13/84. It:( 25) 8 18 9 10 . 0. 7 41 l.-------- 15(12) 8 17-5 6-0.7 as4 1, 16(33) 7. 15 1 7 8 0.2 17 l-17(41) l 7 16 10 1 11 0.5 l 38 l l 18(40) I 5 10 7 l 8 0.0 0 19(13) 3 6 5 I 6-0.6 '32 r 04/09/84-20(32) 8 16 9-l 10 1.1 52' :s 8 l.. 9 J 084/09/81s 21(28) l 04/09/84: 22(5) 4 3 10 ' i 11 0.8 '40 . l 04/09/88: 23(39) l 3 6 6 l 7 1~ 0.2 13. l 0.8 40 1-l 04/10/884 28s(23) 1 6 11-I I I l-I- -- Data Mot Ava'ilable.

No mean or standard data.

' Notes:

1. Units or time are in divisions of the strip chart.

2. Wattage values were determined on a 0 - 500 scale where the' maximum derlection corresponded to

'1000 Watt, hence all values should be multiplied by 2.0. a e. D'

,.n Page 21 ATTACHMENT 6 [.- ' 0UT SHIMS ANALYSIS 1. } l DIFFERENCE, NOMINAL ll DIFFERENCE, NOMINAL. I OlFFERENCE, NOMINAL ~} l DATE REGION (SN) l AVERAGE - FIRST MIN l PEAK - FIRST PEAK I DECAY - FIRST DECAY. l. l (X2 WATT) -(%), (X2 WATT) l (%) 1 (TIME) l (%) l I I l I 204/10/84 1 25(7) I 9 17 l' 8' 9' . O.2 15 04/10/84 26(1) 4 8 7 l 8 0.1 6 '04/10/84 27(2) 8 -15 9 10 0.8 '40 l~ 28(44) 4 8 6 8 0.4 27-1- l 29(35) l 4 9. 6 7' O.2 14-1. l 30(11) 1 0 0 10 11 0.4 36 l l 31(17) 5 1 11' 8 9 0.2 1 14' l l 32(15) 8 1 18 8 9 0.4 I ! 31 33(34) 4 9 T 8' O.0 l' O 34(22) 8 18 l 6 7 0.5 1 . 36 : I 35(21) I 7 16. l 6 . I .I 7 . 0. 6 4 43 36(8) Not collected. 8 04/10/84 37(4) 4 l 7 .ll 10 11' O.8 .I 40-I Mean: I 4.88 10.30-l 7.81 ' 8. 84.l Standa rd: l 2.47 -5.39 l 1.98 1.96-l I ll f ~ e' Da ta No t Ava i lab le. ,)'

No mean or.standa rd da ta..

1. Units of time are in divisions of the strip chart.

Notes: 1

2. Wattage values were determined on a 0 - 500 scale where tive' maximum deflection corresponded to -

1000 Wett,- hence aiI values.should be.multipiled by 2.0. ~ i' 4 0-p .i

r .PageL1 ATTACHMENT 7 DUT SillMS ANALYSIS II UlffERENCE, NOMINAL DlifERENCE, NOMINAL,1 DIFFERENCE, NOMINAL l- -DATE' RECl0N (SN) AVERACE - FIRST MIN PEAK - FIRST PEAK l DECAY - FIRST DECAY (X2 WATT) (%), (X2 WATT) (%) (TIME) (%). 06/25/84 1(6) 3 7 8-

10 2.5 71 06/23/84 2(3) 5 l

9 15 16-1.4 1 47, l 06/23/84 3(37) 2 4 7 9 2.6 65 - 06/23/84 1 4(31) 4 9 13: 15 2.5 63 06/25/84 5(10) 2 5. 6 8 l 2.5 63 06/25/84 6(29) 2 4 10 12-3.0 75 1 06/25/84 7(18) 5 1 11 9 11 2.7-68 i 1 06/23/84 8 38J 3 1 7 l 14 16 2.4 60. l' I '06/23/84 9 26 1 0 l 0 1 5 6 l 06/23/84 10(14 i 2 l 4 ll 8 9' l 1.4' 47 5 06/23/84 11(301 1 2 I 7 8 1.5 43 12(42) l 3 6 7 8 1.2 48 06/23/84 13(16) 1 2 6 7-2.3 58 06/25/84 14(25) 1 2 9 11 2.9-73. l 06/25/84 15(12) 1 2 1 6 I 7 1.6 l -' ' 64 .l 06/23/84 16(33) 2 l. 4-7 8 l 1.8 67-1. 06/25/84 17(41) 2 4 10 12 2.9 73. t l 06/25/84 18(40) 2 4 10 12 3.6 - 72 06/23/84 19(13) 1 2 2 3' 06/23/84' 20(32) 2 4 to 11-2.6 65 N: 06/23/84 21(28) 1 2 10 11' 2.1 62-06/23/84. I 2215) 3 1 7 7 9 1.4 47 06/23/84 -23(39) 3 7' 8 9 1.7 57: .I 06/23/84 24(23) 1 0 0 10 11 1 06/23/84 c25(7) 0 0 1. 12 13 1.0 43 06/23/84 26(1). 2 4 ll-10 11 1.0 33-06/23/84' 27(2) 1 2 1 7 8 2.7-68 06/25/84 28(44) 2 4 1 9 11 .2.0-67 .06/25/84 ??'35) 1 .I 2. I 8 9 2.1' '60 06/95fors 30l11) 1 2 7 '9 2.5 71 Cs/25/84 31(17) 1. 2 8 10 2.4 l 67 -06/25/84 l-112 15) 0-0 . 10 12 -- ' 1. 6 57 i

rI 8

to 2.0 44 06/23/84 1 33 34) 0 0 I I I -- Data Not Available. -

No mean or standard data.

Notes: 1.. Units of time are in divisions or.the strip chart.

2. Wattage values were determined on a 0 - 500 scale where the maximum.derlection corresponded to 1000 Watt; hence all values should be multiplied by 2.0.

.I 4 7 6 l

z____ s -. 1 1 Page 2 ATTACHMENT 7 OUT SHIMS ANALYSIS 11 l l. DIFFERENCE, NOMINAL DIFFERENCE, NOMINAL DIFFERENCE, NOMINAL I DATE' I REGION (SN)- AVERAGE - FIRST MIN PEAK - FIRST PEAK OECAY - FIRST DECAY . l l (X2 WATT) (%), (X2 WATT) (%) (TIME) (%) ~l l I 'l i I 1 I 34(22) 1 2 1 7 9 - 1. 0 50 - ~ 06/25/84 35(21) 3 7 8 9 11 1.2' I 52 .06/25/84 36(8) 3 7 9 11 I 2.2 63 06/23/84 37(4) 4 8 11 12 1 0.8 35' l Mean: 1.89 4.00 8.62 10.14 l Standa rd: 1.33 2.88 2.49 2.61- ? 1 i 'l c. 4 n J. Data Not Available.

No mean or standard data.

Notes:

1. Units of time are in divisions or. the strip ' chart.

2. Wattage values were determined on a 0 - 500 scale where the maximum deflection corresponded to 1000 Watt, hence all values should be. multiplied by.2.0.

9 e i

- r: ~-:1 s Page'1l ATTACHMENT 8 IN SillMS DATA / ANALYSIS 1- - l-NOMINAL }' -'I DATE. REC 10N (SN) STE.*.DY VALUE PEAK AI IN LIMIT DIFFERENCE - I (X2 WATT) (X2-WATT) (X2 WATT) I (%) l I I I l l 1(24) 18 22 4'- 18 .l. 1(24) 19 21 2 10 03/11/84 1(24)- 20 25-5 20. 03/11/84 1(24) 16 20 l' 4 20 l l Mean: 18.25 22.0 3.75 17.0 1 2(3) 22 1 25 3 03/23/84 3(37) 30 1 34 4 ~ 12' 4 12 03/28/84 8s(31) l 30 33 3 9-1 03/13/84 l 5(10) 15 22 l '7 32-l 03/13/84 1 6(29) 20 27 7-26 i l '7(18) 18 23 5 22 1 03/28/84 l.. 8(38) 32 36 4 .1 1. 03/28/885 1 9(26) 31 1 34 3 9 I 03/28/84 ' 10(14) 28 1 31 3 10 03/28/84 11(30) 27 l1 30 3-10-M. '08s/09/84 12(36) 30 1 33- ~3 9 l 04/09/84 l 13(16) ' 28s l 28 is i ts. I.. L 03/13/884 18e( 25 ) 19 27 8 30 3' 15(12) 21 25 4 .16 16(33)- 18 22 l 4 18-17(8 1) 20 24 is 17 l .!.18( 8 0 ) 21 1 2s 3 13 l 1 19(13) 1 23 1 30 7 23 2: -04/09/84 20(32)- 26 ' 1 30 4 13 1 08/09/84 21(28) 29 l-31 l 2 6 Li ~ l 8 ~. 04/09/886 22(5) '25 II 34-9- 26~ 04/09/84 23(39) -l 24: 1 27-3 11 04/10/84; 24(23) i 33 'l 34 1 '3 '08s/10/84 25(7)< l 30 38:. .I 4-12 -l 04/10/84; '26(1) 25 27 2 7 1 l' 04/10/84 '27(2) 21 24 3-13- .l ?28(44) 22 f., 26-4 15 s. 'l 29(35)- 22 1 26 4 15 1 I -- Data Not Available.. . Notes Wattage values were determined on a 0 - SOO scale where the maximum deflection corresponded tou 1000 Watt, hence all values should be multiplied by 2.0. e 4 .I

Page 2: ATTACHMENT.8 IN SillMS DATA / ANAL _YSIS I NOMINAL DATE REGION (SH) STEADY VALUE PEAK AT IN LIMIT 1)lFFERENCE (X2 WATT) (X2 WATT) (X2 WATT).I .(%) ~ -l . 1. 30(11). 18 21 3 .14 E 1 t 1-l' 31(17) 20 25 5: 20 I i 21 1 26 5: I .19 l .32(15 t l 33(34 l l 19 22 1. 3 1-14 34(22 1. -1. 16 24 l 8 'I 33 .'35(211 1 17 20 ~3 .15 ' 36(8) Data not collected due to raulty motor. 37(4) 33 36. 3 8 i l l Hean: 1 23.56 27.69 4.13 15.39 I Standa rd: 1 5.21 4.70-1,82-7.20 I 1 I f s .? ?; .( --- Data Not Available. Note: Wattage values were determined on a 0. 500 scale where the maximum deflection corresponded to 1000 Watt, hence all values should be multiplied by 2.0. i

m._ P W .Page 1-ATTACHMENT 9 IN SHIMS DATA / ANALYSIS 11 l NOMINAL l l } PEAK AT lN LlHIT l-DIFFERENCE I-N DATE i REGION (SN) STEA0Y VALUE i 'l (X2 WATT) l (X2 WAT1) I (X2 WATT). (%) 1. l l 'l I il l ~ 10 l 06/25/84 1(6) 32 35 1-3 l 06/23/84 3(37) ~ 39 43 4 10- - l'e6/23/84 -? 2( 3 ). l 29 34 5 17, 4 l 06/23/84 '4(31) 30 35 5 17 06/25/84 5(10) 22 1 30 8 36 06/25/84 6(29) 35 ll 38 3 9-06/25/84: 7(18) 30 11 30 1 0. 0 06/23/84 8(38) i 26 33 1 7 27 06/23/84 9(26) 1 40 42 1 2 5 ' l 06/23/84 10(14) I 24 28 l 4 17 l.06/23/84 11(30). 24 1 32 l 8' .33

l. 06/00/84.

12(42) 25 1 30 1 5 20 l . 1 06/23/84 -l 13(16) 26 30 1 4 15- .I s 1 06/25/84-l 14(25) 29 l. 34 1 5 17 i L I.06/25/84 l 15(12) 30 32 1 2 7 l 06/23/84 l- '15(33) 29 30 .I 1 3 l~06/25/84 1- -17(41) l 30 34 l 4 13 -l 06/25/84 18(40) 32-1 35 1 3 9

l. 06/23/84 19(13) 25 ll 31 6

24 I 06/23/84 20(32) 28 1 31 3 11 1. I 06/23/84 ,21(28) 28 1 33 5 18- ~ 06/23/84 22(5) 24 32 8 33 06/23/84 l 23(39) l' 25; 28 I 3 12 Q< 06/23/84 l' 24(23) 34 35 1 3 06/23/84. I 25(7)- 29 33' 4 14 ,.e 06/23/84 1 26(1)- 28 35 '7 20. 5 06/23/84 l 2f(2)' 28 33 5 18 l 06/25/84 l 28f44) 29 31 2 7 Ji : 06/25/84 l 2 91 35) 30 38 8 27 06/25/84 l 3 01 11) 27 1 31 4. 15 '06/25/84 l-31L17) 30. 32 .2 '7 06/25/84 1 32(15) 31 34. 3-10 'l l I l' n s O 4-Da ta Not Ava ilable. Note: Wattage values were determined on a 0 - 500 scale where the maximum deflection corresponded to 1000 Watt, hence all values should be multiplied by 2.0. c s

g ;,3 p

p..

Page 2 ATTACHMENT 9 IN SillMS DATA / ANALYSIS II 'l . NOMINAL 1; l DATE REGION (SN) STEADY VALUE PEAK AT IN LIMIT DIFFERENCE ^ l (X2 WATT) (X2 WATT) (X2 WATT) (%)- 11 06/25/84 1 33(34) l 30-32 2 l' 7-l' .34(22) No data available. l t 06/25/84 l -35(21) 26 31 5 19 1 06/25/84 1 36(8) 29 32 3 10 ~, 06/23/84 1 37(4) l 31 34 3- '10 l Mean: 29.00 33.08. 4.08 14.72 Standa rd: 3.86 3.28 2.10 8.70 l l 1 l . c.

f..

a . t.;-- 3 ~ iv -- Data Not Available. Note: Wattage values were determined on a 0 - 500 scale where the maximum deflection corresponded to 1000 Watt, hence all. values should be multiplied by 2.0.

.:):. .y: 4 7 LPage.fi. ATTACHMENT 10 IN SHIMS TRANSIENT DECAY TINC DATA (A.NALYSIS ll: -4 l l .DATE l REGION (SN) l TIME TO DECAY l i I I 1 . I.06/25/84 l-1(6) i 3.8 I l 06/23/84 1 2(3) l 2.0 ~.' I~ 06/23/84 ' l ,3(37) l 2.4

1. 06/23/84 4(31) i 2.0 06/25/84 5(10)

.l 2.8 1 06/25/84 6(29) 1 3.6 1 06/25/84 7(18) i 4.4 I I.06/23/84 'l 8(38) i

3. 8.

06/23/84 I 9(26) l' 1.4 06/23/84 1 10(14) i 3.8 '06/23/8f4 l 11(30) I 2.2 06/00/84 12(42) l 3.2 06/23/84 13(16) i 4.0-06/25/84 14(25) 3.8 1 06/25/84. 15(12) 1.6 1 06/23/84 1 16(33) 1.6 'l 06/25/84 17(41). 2.0 06/25/84 '18(40)- 3.2 1 06/23/84' .19(13) 2.2 06/23/84 20(32) 3.4 06/23/84 21(23) 1.8 06/23/84 1 22(5) 2.6 06/23/84 l 23(39) 2.6 06/23/84 l 24(23) 1.8 06/23/84 1 25(7) -2.8 06/23/84 -I 26I.1) 2.4 06/23/84 l 2 71 2) 4.0 06/25/84 I 2 81 44) 4.4 1 06/25/84, i 29L35) 4.4 l 06/25/84 1 30(11) 4.2 1 06/25/84 1 31(17) 1 2.8 4 06/25/84 l 32(15)- le 2.4 I - ll 06/23/84 ;1 33(34) l 1.8 l 34(22) l' 1.8 l 'l l I -- Da ta No t Ava i l a b l e. Note: Units of time are in divisions or the strip chart. 4 w h

}- ~ Page 2 ATTACHMENT 1Q IN SHIMS TRANSIENT DECAY TIME DATA / ANALYSIS ll l l } DATE . REG I ON ( SN ) l TIME 10 DECAY l i l 06/25/s4 35(21) 1.s l 06/25/a4 36(s) I 2.0 1.-D6/23/84 l '37(4) 1-1.6. I 1. I l Mean: I* 2.77 l l Standa rd: l 0.96. l I i 1 i' l q.- Data hot'Available. Note: Units or time are in divisions of the strip chart. T 9

.,~.~ . - ~ ~ _. -.. r.; Page.1 ATTACHMENT 11 INDIVIDUAL CrDOA SHIM SEQUENCE VARIATION ANALYSIS l 1 I OUT SillM l IN SHIM 1 I I I I l-l MEAN PEAK

l

' MEAN DECAY NO. OF-l MEAN PEAK" i MEAN DECAY l No. OF l.DATE I REG 1088/(SN) i FIRST PEAK (X2 WATT) l FIRST DECAY TIME / DATA l1. (X2 WATT) 1 TIME / l DATA I -I-l (x2 WATT) (STANDARo i TIME (STANDARD PolNTS ll (STANDARD l (STANDARD-1 Po1NTS I l 'l DEVIATION) i DEVIATION) USED l DEVIATION)' DEVIATION) l USED. I I I I I I I -l l i I I i 1 - l 08/23/84 HSF/(7)' I 86.00 1 92.57 1 0.4 0.94 7 l 80.43 0.69 1 7 i I I (1.51) i I (0.10). I (0.53) (0.11), i 1 L i i 1 i l~ l l I I 8 1 I I I I I l -106/28/84 HSF/(11) l 84.00 l 94.14 1 0.2 1 0.83-l 7 'll 81.14 l 1.0 -7 1 1 I I I (1.07) 1 (0.08) i II-(0.38) l .(0.13) l I i i 1 1 I I I I. I I I I l 1-109/28/84 HSF/(26) 1 88.0 l 97.14 1 0.4 1 0.86 7 81.14-l 0.94 7 R' I I I (1.07) 1 I (0.10) I (0.69) I (0.22) i i l I i i I i I i 1 1 I I I I l-108/18/841-HSF/(29) I. 88.0 1 96.78 1 0.2 1 n.62 -l 9 1 83.63 0.75 l-8 I I i 1 1 .(0.67) 1 (n.16) I 1-(1.51) .(0.09) 'i l i l i l I I I i I i I I I I I il I-1 l 133/23/841 3/(37) 1 80.0 1 89.47 0.6 l 1.70 1 17 I 79.22 1.36 l 7-1 I l -l l (1.37) l (0.14) l I (1.20) (0.17) l l l I ~ 1 1 I i 1 l 1 'l 1 l 1 11-1 I Ic3/28/841 10/(14) 83.0-96.47 0.4 l 1.27 l -17 l 84.14-1.83 1 7 ^,' l -(2.21) l-(n.17) I 1: (1.57) (0.36) I l I I I I 1 I I i 1 l l:3/28/841 11/(30 1 82.0 1 93.94 0.8 1 1.40 'l 17 81.14 2.08 l 7 l (1.14) I (0.14)- 1 I (0.38) I (0.38) l l l I I i 11 I I I I I I I I -1 I l .Il 1-l 106/23/841 16/(33) 1 78.0 1 87.63 1 0.6 l - 2.72 - l 8-II-75.50 1-1.78 I 8 l l l l l (1.30) I 'l (0.81): l ll (1.77) I (0.31) I i i i l' I I I i ll l l l

Excludes the First peak.

' Itote: Wettage vaiusa were detereined on a 0 - 500 seaie whore the meximum deflection corresponded to 1000 Wett, hence all values.should be multiplied by 2.0.'

.~ ~{t Page 2 ATTACHMENT 11 INDIVIDUAL CRDOA SHIM SEQUENCE VARIATION ANALYSIS l l l OUT SillM l IN SHIM l 1 I l 1 l l l MEAN PEAK

I

.MEAN DECAY NO. OF l MEAN PEAK

MEAN DECAY NO. Of l DATE I REGION /(SN) l FIRST PEAK l (X2 WATT) l FIRST DECAY TIME /

DATA I (X2 WATT) TIME / DATA l l l (X2 WATT) l (STANDARD l TIME (STANDARD POINTS l (STANDARD (STANDARD PolNTS I 1 l l l DEVIATION) l DEVIATION) l USED l DEVIATION) I DEVIATION)~ USED .I i 1 l I I I i 1 .I I I I i 1 1 1 106/25/84 35/(21) 1 76.0 1 85.0 l 0.6 1 1.98 1 9 73.75 1 3.35 8: l l l (1.0) l l (0.32) 1 (1.67) 1 (0.58) I e 1 1 1 I I il-l l ~ ' ~ ' 1 I i i i i i il I i 106/25/841 36/(8) 1 7s.O a7.s8 1 0.6 1 3.0 1 a ll 77.63 1 2.40-l 8 I I I (0.83) l l (0.15) I 11 (0.74) I ,(0.21) l l I I I I i 1 11 1 1 'l l ~

Excludes the first peak.

Note: Wattage values were determined on a 0 - 500 scale wbsre the maximum deflection corresponded to 1000 Watt, hence all values should be multiplied by 2.0. j

7 ' 2 EXPLANATION OF WATTAGE TEST EVALUATION-SUPPORTING DATA This data was coll'ected.on either of (2)'Esterline Ang'us Model A 601C: Graphic (recording) Wattmeters, rated at 100 volts' Land 1000 ' watts,. fu11 scale!-(3 phase, 3 wire, 60 Hz), serial numbers-182698, 182699, calibrated July'7, 1984, with a guaranteed accuracy of 1% full scale- ~ 3 (10s)~ Precision, as indicated by peak and nominal valu~es reached F 'over.many shims'at approximately the same drum condition, appears to be about 1 watt. This means, provided voltage-conditions are-kept - constant, the readings can be '. compared between-shims o_n a given chart,.-so that very ' precise conditions can be achieved, which-is important for the use.of the wattage test done.here (Note variations in voltage over the time required to perform the test will. generally not pose a problem, as.these_are typically slight). All-wattage values are recorded assuming a precision ofil watt. Also-note.that voltage variations have.no effect on the watt recorder's i ability to accurately determine. wattage; rather, they change the j motor operating point so that power consumption, for the same load, will be different. Finally, note that absolute determinations of-i power in watts, for comparison against FSAR, O&M, and other values, l are admittedly a -problem because the test did not include voltage - data; the proposed procedure corrects this problem. Consequently, j these comparisons.and any conclusions should be very tentative. Remember'the guaranteed accuracy is only'110w, even if the precision is lw. 4 } All data values were recorded on a 0-500 scale where 500 corresponded-to 1000w. Hence the reading in watts is that recorded -times-two. Also, the two wattmeters were adjusted for different chart: speeds on the slow speed scale, as follows: SN 182698 (East Rx) 5 sec/ minor division SN 182699 (West Rx) 2.5 sec/ minor division I Because the speeds for various charts were different, evaluation of overall mean decay times for reference purposes was intentionally not done. -This has no effect on the proposed test, a any given j determination of position is done on a single wattrecorder. l Out Shims Data I, II These list values for minimum. wattage during the transient, peak-i wattage during the transient, and decay time (chart division units) for.-the two general transient types: (1) those. starting at-th?:in, limit,.and (2) subsequent transients with the drum wrapped.. Note C that with the drum wrapped, the nominal steady value is the minimum - value, since no dip occurs. Out Shims Analysis I, II These compute-differences, and express these' in : percent for~ comparison against test requirements. One observes that in' a few l instances, actual "in" conditions would -not be~ met by the te'st requirements, even though limit switch behavior indicated that in fact, the rod pairs were "in". 1-s rp-,-- m-p. ~ p ,n ,o e, -ew.s -4 ,e r ,,-'rr v ,- r,<;

4 g 2A_.,, . a 2 2 f -Att'achment 12 In~ Shims Data / Analysis'I, II

These:~ list valuesafor steady final wattage' for in shims leaving the

-drum wrapped, and. final: peak wattage for sh'es that. terminate at the - "in"' position, as!well as.the differences and percentage difference. In ' Shims Transient Decay Time Data / Analysis 1II- ~ This,has1 no relevance to the test, but was included to-show typical-in shim decay time variation, for information. Individual CRD0A Shim Sequence. Variation Analysis This sis 1the summary of detailed. evaluation of; shim sequences on - individual CP.00As to determine the variation in nominal-values for out.-peak (drum wrapped), out-decay,_ in peak, and in decay. The purpose.is to illustrate the mean and variation in these parameters, to allow comparison against the tested ~ value, to examine Ethe - significan:e of the variation: First. Peak vs. Mean Peak 4 First Decay vs. Mean Decay 4 - In shim data is again provided for information. Note that 10 shim sequences from 10 different mechanisms tested on various dates ~ were selected. Selection was random, with the exception that several charts could not be used due to. incomplete or-- multiple shim activations during the -transient ' periods,- which required elimination because peak or-other values could not-be i clearly defined. The proposed test also eliminates this possibility by requiring complete repition of the sequence, should this occur. i 'I ) 4 j i i i- ?

PU_LIC SERVICE. COMPANY OF COLORADO TSP-30 e FORT ST. VRAIN NUCLEAR GENERATING STATION p Attactunent 13 TITLE: TECHNICAL SERVICES PROCEDURE NO. 30 EVALUATION OF SHIM MOTOR WATTAGE CHARACTERISTICS ISSUANCE AUTHORIZED BY PORC EFFECTIVE REVIEW DATE 1.0 PURPOSE This procedure describes the methods used to obtain wattage recordings, review the recordings, identify anomalies, establish "in" rod position and document the recordings. 2.0 APPLICABILITY This procedure applies to the Technical Services Department's periodic responsibilities with regard to monitoring shim motor performance. All in-reactor rod movement will be done by the Reactor Operator with the Shift Supervisor's concurrence as indicated in SOP 12. Technical Services' responsibility will include monitoring of the watt recorder on the MCC and requesting the desired rod motion per S0P 12 through the Reactor Operator / Shift Supervisor. Adequate shutdown margins must be maintained at all times as indicated in the Cycle Safety Analysis or by GAUGE calculation; 3.0 OBJECTIVES To establish a data base of shim motor characteristics. To establish condition of absorber strings and/or. drive mechanism under anomalous conditions. To determine rod "in" position in the event analog and digital ("in" limit switches or position potentiometers) indication is lost, or to verify existing indication. ~ 4.0 PROCEDURE 4.1 Initial Conditions 4.1.1 Recording wattmeter is connected to the CRDMCC with the region (s) to be te,sted. 4.1.2 If the wattmeter is not connected to the desired CRDMCC obtain a TCR through the Results Department and request an electrician to connect as required. l FORM 372 22 3842 j

" % v V dQ (O V s vs

.w ~ ~ TSP-30 Issue 1 0 Service-Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 17 pusuC SERVICE COMPANY OF COLORADO 4.1.3 Insure the wattmeter is operational..(Turn power "on", check to see pen is correctly set and inking, l and adequate chart paper is installed, or perform other checks as appropriate for the instrument.) Zero the' instrument or otherwise identify "zero" level, once the wattrecorder is on. All following references to wattage are with respect to this "Zero" level, if the wattrecorder is not exactly Zerced. 4.1.4 ' Verify the wattmeter-calibration date and record on TSP-30A. 4.1.5 Obtain a calibrated stopwatch and record calibration date if a timed shim sequence is to be performed. 4.1.6 Attach a voltmeter-(multammeter) in the voltage measurement mode across the individual phase ground terminals for phases A, B, and C. Record voltages on TSP-30A (see diagram TSP-300). 4.2 Procurement of Data 4.2.1 Request Shift Supervisor's permission to perform shim motor wattage test. Identify Region involved and reason. Testing will normally only be done while shutdown. For normal CRDOA configurations the requirements of SOP 12-02 must be met: Not more than 2 CRDOA absorber pairs at positions other than fully inserted, including those of any CRDOA removed from the reactor (i.e., if any CRDOA is removed, its absorber pairs must be considered fully withdrawn). For other configurations (examples, (1) low CRD0A in a high region, (2) ICRD reinstalled, etc.) not explicitly covered by the cycle SAR, a GAUGE run verifying the shutdown margin (2 0.01) must be performed prior to rod movement. Review Attachment B to become familiar with watt recorder interpretation. 4.2.2 Request Reactor Operator to notify-Shift Supervisor i and then exercise or shim the desired control rod pair in reactor. If monitoring is to be done on a CRDOA in the HSF, request the Maintenance Refueling Supervisor or designee to exercise control rods. FoAMIC3372 22 3643

s , a .u f.r. TSP-30 Issue 1 0$9tVlC9" Public. FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 17 PUBLIC SERVICE COMPANY OF COLORADO 4.2.3 For each CRDOA to be monitored for trending / monitoring purposes, it is desired to obtain recordings of one full in and one full out movement. Record control rod position at statt, finish, and at appropriate places deemed necessary. Additional recordings, such as running the control rods "out" and "in" in twenty inch increments may also be obtained. All position information may be marked on the recording chart. 4.2.4 To establish "in" rod position with watt recorder perform the following while obtaining watt recordings: Sequence a a) Scram the rod pair (pull the fuse, scram the Reactor, etc., as appropriate). b) Obtain a calibrated stopwatch and prepare to time. Shim "out" for 15 seconds. (This will not have a significant effect on core reactivity since the total rod travel will be about 16 inches.) Record time of "out" shim: a b c c) Shim "in" for the exact time recorded above. The rod pair should again be at the fully inserted position. d) Scram the rod pair. Sequence b e) Repeat steps 4.2.4 b)-4.2.4 d) above. Sequence c f) Repeat steps 4.2.4 b)-4.2.4 d) above. a FORM (Cl372 22 3643 ~

A... TSP-30 Issue 1 O service

Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 17 PUBUC SERVICE COMPANY OF COLORADO 4.3 Evaluation of Data 4.3.1. "In" Position Evaluation a'

For an inserted rod pair, the cable drum must wrap to raise the rod pair. As this occurs motor load will increase. For the "out" shims above, observe a wattage trace which shows an increasing ' steady' value after the starting peak occurs, as seen below.__ _ _ p 16Vw - M" ~ eq u

l

& c-tosee + Record the minimum wattage for each "out" shim: la lb Ic Record final wattage for each "out" shim: 2a 20 2c FORMICl372 22 3643

u TSP-30 Issue 1 0 service

Public FORT ST VRAIN NUCLEAR GENERATING STATION Page 5 of 17 PUBLIC SERVICE COMPANY OF COLORADO b)

For the "in" shims, observe an increase in the steady wattage towards the end of the shim as the drum unwraps, as seen below: P Ga i f. 46= 1 l

-e see s Record the nominal wattage after the starting 4

peak for each "in" shim: 3a 3b 3c Record the final wattage for each "in" shim: 4a 4b 4c c) If the at,ove observations are made, and if for items 1 and 2, cases a through c, 2 1 5= 2 X 100% > 5%, and for items 3 and 4, cases a through c 4 3 6= 4 X 100% > 5%, the rod maybe considered "in"; continue to step 4.6 below. Record: (> 5%) Sa 5b Sc ~ (> 5%) 6a 6b 6c d) An. exact repetition of the above sequences, 4.2.4 a)-f) and 4.3.1 a)-c) may be done as many times as desired. Any sequence for which the above conditions are met may be used to conclude that the rod pair is "in". FonM(C1372 22 3643

TSP-30 Issue 1 0 service

Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 17-PUBUC SERVICE COMPANY OF COLORADO 4.4 Detailed "In" Rod Position Test and Evaluation a.

Theory Both the_ peak wattage and decay time for an outward shim - starting at the fully inserted position varies from those of a shim starting with the drum sheave wrapped. This is due to the decreased power to establish motion, in conjunction with a quicker decay to the final steady value due to the more rapid acceleration when the rods are not immediately required to rise upon shim initiation. Decay time is the time to reach a minimum wattage value during the shim, or the time to reach a value within 2 watts of the final extrapolated steady value, or the time of the shim, whichever is shorter. b. Data Procurement NOTE: Any RWP or incomplete shim will require repeating the test sequence. Sequence a 1) The control rod pair is scrammed; reset the scram breaker. Start the wattrecorder when ready. 11) Shim outward for 15 seconds; wait 10 seconds. iii) Perform 11) again, exactly, iv) Perform 11) again, exactly. v) Shim inward for 15 seconds; wait 10 seconds. vi) Perform v) again, exactly. vii) Perform v) again, exactly. Sequence b viii) Repeat steps 1) - vii) above. Sequence c ix) Repeat steps 1) - vii) above. l FORM (Cl372 22 3t43

~ ~~ TSP-30 Issue 1 0 Service" Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 7 of 17 PUBLIC SERVICE COMPANY OF COLORADO c. Evaluation 1) The wattage record will indicate three sequences, each a series of 3 "out" shims and 3 "in" shims, of exactly the same duration. . y..- - k a6w m .o. ,a 1 t (s<c) p,ga. m 4,1 ,1,1 d /ecc) 11) Record the wattage peaks of each

shim, consecutively, below:

Sequence a "out" shims shim 1 shim 2 shim 3 la 2a 3a "in" shims shin 4 shim 5 shim 6 4a 5a 6a Sequence b "out" shims shim 1 shim 2 shim 3 lb 2b 3b "in" shims. shim 4 shim 5 shim 6 4b Sb 6b I FoAMtC)372 22 3843

TSP-30 Issue 1 0 Service ~ Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 8 of 17 rusuC SERVICE COMPANY OF COLORADO Sequence c "out" shims shim I shim 2 shim 3 le 2c 3c "in" shims shim 4 shim 5 shim 6 4c Sc 6c iii) Record the decay time of each shim, consecutively. Decay time: time to reach a minimum or stable value (within 2 watts of extrapolated final steady value), or time of the shim, whichever is smaller. P i ~ f;Y '4 (see) ~ ~ decay t.ske j(see) P 2e Honoff VelWC s, l Sequence a W #""f i""- W t'(tre) "out" shims shim I shim 2 shim 3 l'a 2'a 3'a "in" shims shim 4 shim 5 shim 6 4'a 5'a 6'a FORMtC1372 22 3843

L TSP-30 Issue 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 9 of 17 O Service ~pusuc service ' COMPANY OF COLORADO Sequence b "out" shims shim I shim 2 shim 3 l'b 2'b 3'b "in" shims shim 4 shim 5 shim 6 4'b 5'b 6'b Sequence c "out" shims shim I shim 2 shim 3 l'c 2'c 3'c "in" shims shim 4 shim 5 shim 6 4'c 5'c 6'c j iv) For each sequence, average 11) items 2-3 2+3 =7 2 and average iii) items 2'-6' 2'+ 3'+ 4'+ 5'+ 6' =8 5 Sequence a Record 7 and 8: 7a 8a Sequence b Record 7 and 8: 7b 8b Sequence c Record 7 and 8: 7c 8c FORMICl372 22 3843

. TSP-30 Issue 1 0 $9tVIC9" Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 10 of 17 PUBUC SERVICE COMPANY OF COLORADO If for each sequence, y) 7 1 X 100% 2 5% 9= 7 and l' X 100% 2 50%, 8 10 = 8 the rod pair may be considered "in"; continue to step 4.6. Sequence a Record 9 and 10: (>5%) (250%) 9a 10a Sequence b Record 9 and 10: (>5%) (250%) 90 10b Sequence c Record 9 and 10: (>5%) (250%) 9c 10c If the result is negative, notify the Shift Supervisor and Technical Services Engineering Supervisor that "The control rod pair in Region (give Region) cannot be considered inserted"; continue to step 4.5 if directed. 4.5 Absolute "In" Position Evaluation NOTE: This test should only be performed if both the analog / digital position pots are n'ot correctly indicating and the "in" limit switches are not picking, or there is evidence that the multijaws' coupling connecting these indicating devices is

failed, causing readings inconsistent with the rod motion, or if there is an absolute need for independent verification of rod pair position.

I FoRMICI372 22 3843

TSP-30 Issu)-1 0 Service" Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 11 of 17 PUBLIC SERVICE COMPANY OF COLORADO Because_ this act'ivity places a high risk on breaking the multijaws coupling, Station Manager approval is required to proceed. Approval to proceed: Station Manager Date/ Time This is the most definitive wattage test for determining "in" position, a. Theory A shim in which the motor raises th~e control rod pair, nominally referred to as outward shim, performed by shimming in the "out" direction, differs from an inward shim due to the differences in the peak and steady wattages, for the case where. the cable drum is wound approximately k turn so that the moment arm is developed. At the fully inserted position, the moment arm is zero, as the rod pair hangs free from the drum attached-by the anchor ends. At this point, the transient peak for an "out" or "in" shim is the same, although under normal conditions only an "out" shim may be accomplished, as_the picking of the "in" limit switches precludes shimming in the inward direction. Note that if the "in" limit switches fail or are opened up, shimming in the inward direction is again possible, except that now the cable fs wrapping around the drum sheave in the. reverse direction. Hence the shim motor is essentially performing a' raising transient, which requires more wattage than an insertion transient. Thus the shim motor wattage transient will. appear as if ac "out" shim is being performed, even though the shim is in the "in" direction. The crux of this test is to observe the change in the motor transient performance that will occur if the rods l are at the fully inserted position. l b. Data Procurement l NOTE: Any RWP or incomplete shim will require repeating 'the test sequence.' ~ FonMicl372 22 3643 - F

TSP-30 Issue 1 0 SerVICO Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 12 of 17 PUBLIC SERVICE COMPANY OF COLORADO WARNING: The following sequence must be performed exactly to minimize risk of jamming the assembly. Sequence a 1) The control rod pair is scrammed; reset the scram breaker. Start the wattrecorder when ready. ii) Shim "out" for 10 seconds; wait 2 10 seconds. Shim time: a b c iii)- Shim "in" for 10 seconds; wait 2 10 seconds. Shim time: a b c iv) Shim "in" for 10 seconds; wait 2 10 seconds. Shim time: a b c v) Shim "out" for 10 seconds; wait 2 30 seconds. Shim time: a b c Sequence b vi) Repeat 1) through v), exactly. Sequence c vii) Repeat 1) through v), exactly. i c. Analysis 1) Determine the final wattage values for the shims in item b. ii); if no steady value was obtained, note. l l la lb Ic l l 11) Determine the steady wattage for the shims in item i

b. iii).

This will correspond to the minimum wattage seen during thase shims. 2a 2b 2c FORM (Cl372 22 3643 .e

+ ^*eA -TSP-30' Issue 1 OSerVICe Public FORT ST. VRAIN NUCLEAR GENERATc.NG STATION Page 13 of 17 PUBLIC SERVICE COMPANY OF COLORADO 111) Calculate for 1) and 11), items a through c above 2 1 3= 1 X 100% iv) Determine the final' wattage for the shims in item

b. iv); if no steady value was obtained, note.

4a 4b 4c v) Determine the steady wattage for the shims in item

b. v). This will correspond to the minimum wattage seen during these shims.

Sa 5b Sc vi) Calculate for iv) and v) items a through c. 4 --5 6= 4 X 100% vii) If for items a through c, 3 > +25% and 6 > +25% Record 3 and 6, items a through c, below: (>+25%) 3a 3b 3c (>+25%) Then the rod pair may be considered "in"; continue to step 4.2.5 a 5). If the result is _ negative notify the Shift Supervisor and Technical Services Engineering Supervisor that "The control rod pair in Region (give Region) cannot be considered inserted"; continue to step 4.6. 4.6 Disable Rod Motion FORMIC 1372 22 3642 l

TSP-30 Issue 1 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION. Page 14 of 17 SerVIC9" PUBLIC SERVICE COMPANY OF COLORADO To insure no rod motion for shutdown rr.argin purposes, instruct the~ Reactor Operator to pull the fuses on that Region and write a System Status Tag precluding rod motion for that rod. pair. 4.7. Transient Evaluation 4.7.1 Normal Operation a) For shims that begin/end at more than 10 inches position, the wrapping / unwrapping behavior in a. is not observed. b) For-the "in" shims, observe an increase in wattage at the initiation followed by decay to a steady value over the next 10- seconds. Nominally the wattage should peak at 140-150 watts and decay to 40-50 watts. nsa a P

6 s l

efact stop g c) For the "out" shims, observe an increase in wattage at the initiation followed by decay to a steady value over the next 10 seconds. Nominally the wattage should peak at 160-180 watts and decay to 80-100 watts. - to 4a P l 90a - t t 40 tt gg l l - FORM C372 22 3643

~ U. - m TSP-30 Issue 1 0Public FORT ST. VRAIN. NUCLEAR GENERATING STATION Page 15 of 17 SerVIC9" PUBLIC SERVICE COMPANY OF COLORADO -l d) Over the duration of a continuous "out" shim from the fully inserted position, a gradual rise in wattage is seen of ~6 watts, due to the spiral wrapping of the drum sheave slightly changing the sheave moment arm. p 9pa. o I L 5 +(min) e) Over the duration of a continuous "in" shim from the fully withdrawn position, a gradual decline in wattage is seen of ~6 watts due to the unwrapping of the drum sheave. P ge_ _~. o n 1 3 4.7.2 Rotor Seizure a) Rotor (hence drive mechanism) seizure is indicated by nearly instantaneous changes in wattage of very large magnitude. Should these be observed, rod motion should be stopped and evaluation of circumstances performed. 440as P 90 s I l 1 u.eure-thee) l l FORM (C)372 22 3643

u--- L ' .:,8 : TSP-30 l Issue 1 O Public ' FORT ST. VRAIN NUCLEAR GENERATING STATION Page 16 of 17 SerVICC" PUBLIC SERVICE COMPANY OF COLORADO 4.8 Documentation Upon completion of monitoring, record the region that was tested or indicate HSF if conducted there, the CRDOA serial number, primary coolant temperature and moisture level as available. This information can be recorded on the wattage recording. Sign and'date the chart recording and attach to this procedure. This information is recorded on Attachment TSP-30A. 4.9 Review Review the recordings _for unusual wattage. Normal steady readings are 90 watts during withdrawal and 44 watts during insertion; transient peaks should be 70 to 95 watts. Normal readings are 90 20 watts out 44 20 watts in 4.10 Notification If abnormal readings are obtained notify the Technical Services Engineering Supervisor. 4.11 Historical CRDOA Data File copies of anomalous chart recordings with the Technical Services Control Rod Historical Information. Complete the Evaluation Summary and forward to the Technical Services Engineering Supervisor for review. 4.12 Records Transmit the original attachment and chart recordings to Record l Storage; retain copies in Technical Services files for review. Also transmit completed evaluations and recordings for any position evaluations.

5.0 REFERENCES

S0P 12 GA-9806, Operation and Maintenance Manual, CRDOA WATTMETER USE TO DETERMINE INSERTED ABSORBER STRING p0SITION, Engineering Analysis by Jim Eggebroten i FORM (C) 372

22 3643

~ _ L.. _. 2:-.- 2.: ?_

,e.

TSP-30 Issue 1 0 SerVICO'" Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 17 of 17 PUBLIC SERVICE COMPANY OF COLORADO 6.0 ATTACHMENTS Attach. TSP-30A, Evaluation Summary Sheet Attach. TSP-308, Typical Transient Analysis Sheet Attach. TSP-300, Sample Transient Records m. FORMiCl372 22 3643

~ =.. ~ ~ w Attach. TSP-30A~ Issue 1 O service

Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of I PUBLIC SERVICE COMPANY OF COLORADO 1

EVALUATION

SUMMARY

SHEET Engineer / Technician: Date: QC Representative: Wattmeter Identification: Calibration Date: Stopwatch Identification: Calibration Date: Voltmeter (Multameter) Identification: Calibration Date: Location (check) Reactor HSF If Reactor: Region Moisture (if available) ppm

F Inst (MM9305, MM9306, MM9307)

T Cire Inlet

F CRDOA SN (if available)

Phase-to ground voltages during shim: A B C (Not required for position determination.) 't

SUMMARY

OF OBSERVATIONS Completed By: Date: Date: Technical Services Engineering Supervisor ("In" position verification and abnormal readings, only.) Make copy for Technical Services files and forward criginals to Records Storage. FORM (C1372 22 3643

~ c 4-s ' ~ Attach.~ TSP-308~ .Iosue 1 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION .Page 1 of 1 Service ~ PusuC SERVICE COMPANY OF COLORADO WATTMETER INTERPRETATION leoa r OUTWARD.5HIM p f coou w2ACOFD I - ou a go - 1 he*y ##e-l g;me(wc) ~ = 168 e OUTWARD _ SHIM _. p 5:"OLL - /N Mst f"f 6N 90a yi - - I. l d e ca y ti;e < ! g;,,se (sec) = O i, s D IEWARD #HI* IS6 *0 bEUM WEAW O 50 w. qgs I $4enf WMC, 9 g (ggg) l ' M C D ^^

P 166.J Ft)LL=IM YO$ l*1"ICN I

6 "#
ccoy T/W r

O4 t<Me (:ee) FORM C 372 22 + 3043 L

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- rusuc sERWCE COMPANY OF COLORADO 4 iMh N s e ,th N J ( <g .p s N.,, s s N Q --- N N N q _ g N s s ggg s ~ s ~ s 'g g g g b % s , N g ] '9 r p, s 'a s N N -~--- ~ s s N s N g g g g ' N g g s s l h, s N s yg N g = I s s N % s s s s s U N 4 g I g, N g 4 s s k s s s I s s s U % g g s,s g s s s g f. 'h g g =% s ~ c,- gM I <6 c p C > 5 s ( f-k > s 1 r -- N 1> N c, N 'N s ,e > s y 6 L N c> N g ~ s s ~- N s 1 g t '5 ' N N,,,, i zi ci c7 lF I c. p h t c p N s bg c 7 % i-., s c ) N s g g g, s ,J ( s s x x q s.,u e 3 ds4 h f sN CD N N N l s N s ~- 'a N g s s g g s ,s s s s s g, N, N %,s 4 N s s s s s b g j ' N N .g i gJ t s s s s .c N N g . ga g s s i., 1 N + i,s .I s s j w s s f a 3 s s N N N.y s I C C s s s 1 m s \\ { N j N N s s s s s 4 N ---===~ F s g s s% s H ,i s g w. s .U N s ,q, g N 7 % I rifirrr PORMC372 22 3851 i r 1 ~_ _. _ _ __ -__ _ _. _ _.. _ - - _ _. _. _... _ _ _ _ _.... _ _ _ _ _ _. - _ _ _ _ _, _ - _ _ _ _ _ _.. _ _ - _. _ _ _ _ _ _

Attach. TSP-30C Issue 1 0 Service ~ Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 9 rusuc senvics comeAmy or cotonaoo %{}'N 's N N . tp ( l N e 4-N N q[ F - N s s s g i j p 'a= =, N = -w I mi, g h %,. J g N w R 'i-h s N = s 'h, N s % g g N N --==. N - + N = --= < r s N 5 C I ' g b 8 C I 9 ~ ~ c > ~~ }{QQ3 + s e, s s 4 %,c s s l a-4 ,=, N a N N = N g s N s a ~*-* s s i 'a g 4 [ c p c i---- N ~ 4 p h t c p g 6 6 c I a 1 6 c > = n,, 4 % -~~ s t ~~ w c h ~~- N N g s 1 '9" E ',h N N N N s g m ~ s g s g s g N N s 5 a 9 m g g f, ' $d } N g s ~ s N s s r ,,,,N , N ~- y s s s N --=. --g g s g g s s N ( s s s s l M$ N '= l s , s ~ ~ s ,,i,,, g s s g s s g g N s s ~ m, % g g ~~- N .gV'---- + s N g -~ ad N s NA N s l . 7 s. s,. ,% s s t I FomM10372 22 3043 --,r-r---n-- ..,-.4-..v----r.,-,,-mn. -ww--m. ,m., n,., - -,,, -- ..,--.,n --n,

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m_ ;. __._. - - 4 _O&M REFERENCES-TO MOTOR WATTAGE- - Page 47: 60 watts - maximum . normal out wattage beyond : which.- reliable scram capability not assured. Page 64: At motor supply voltage of 105V:

22. watts - normal insertion wattage 72 watts - normal withdrawal. wattage Page 75:

At motor supply voltage of 105V: 72 watts - normal withdrawal wattage difference between normal and value-18 watts beyond which' scram may not occur due to high friction. + 9

' a he ' Attachment 15' V FSAR REFERENCES 1TO WATTAGE The!' rod.with'drawal. reading,:with the additional 1.0 to 1.3 in-lb torque applied to the motor, was 90w compared to a normal (i.e., "as built"), wattage reading of 72w. Page 3.8-5 4 4 e 4 l I 6 g4 __e.. ,o - - + y y

SDP 12-01 Issue 15 puhllC FORT ST. VRAIN NUCLEAR GENERATING STATION 'Page 17 of 20 service'" PusuC SERVICE COMPANY OF COLORADO -ATTACHMENT 7 TO P-85040 5.6.11 Bypass the rod out limit. 5.6.12 Obtain Reactor Operator permission and withdraw rod to full retract limit. - 1000 2. l

1. - Section 5.7 is the result of an NRC commitment..

l. Reference G-84392 and responses. DO NOT DELETE' l 'without issuance of comparable controls.*#* -l. 5.7 No "In Limit" Light On Fully Inserted Rod. 'l 5.7.1 Verify there is no slack cable indication. l 5.7.2 Reset Scram per Section 3.2 l 5.7.3 First withdraw affected rod pair to a digital l indication of -6". Do not first insert the rod, l since damage to position potentiometers could I occur. l 5.7.4 Manually insert rod until rod motion stops or a l digital indication of 0.D", whichever occurs first. l 5.7.5 Verify "In Limit" light is lit. If not, initiate 1 SSR. j [ h o I 1 50W ICl 372 22 + 3M3 ' .y ,,_.-,_.---,,_,.y_. y,- ..,,---~~.,y..,,,..,7, e,-, -,,,g_, ___..,-.,_m-m- y~,-.

g .~ ATTACHMENT 8 NUMBER

84-17 TO P-85040 ISSUE 2

DATE 1/31/85 SYSTEM 11 OPERATIONS ORDER ATTENTION: lXXXXXXl lXXXXXXI lXXXXXXl IXXXXXXl l l 1 l i I I I SS RO EO AT . Note: Initial when order is read. .i f 1 i i i CR0 PURGE FLOW LOST The loss of Control Rod Drive (CRO) purge flow is alarmed in the Control Room. The intended response to a low purge flow alarm is: 1. Review purified helium flow, pressure and temperature indicatichs for abnormal indications. 2. Verify by local indication that flow alarm is valid. 3. Attempt to recover purge flow, gb g6 ~ .r..

'~

LL_

3 + lNUPSER

84-17 ISSUE 2

DATE 1in ins SYSTEM 11 '4. If available, switch to the standby helium purification train. If the above steps do not restore purge flow, reactor power will be reduced to less than 25 by. following established operating procedur'es. High Moisture in Primary Coolant i 1. Average core outlet temperature k 1200*F and chemical impurities-k 10 ppe as determined by Health Physics. Reduce core-outlet i 1 temperature-to < 1200*F. Further reduction of core outlet

temperature may be necessary to remain in the Ifmited acceptable

) range on Figure 4.2.11-1 in the Technical Specifications. 2. Average core outlet-temperature s 725'F. a. If primary coolant ' dew point temperature is equal to or greater than 60*F, scram reactor per EP 8-1 and notify j ,$uperintendent of Operations. i 0 4 i i i J .. NAAsu' Sup4rintencept. Opefations (or) Station Manager I 3 e 1 cac g i \\ 4 l- , _ ~. _, _ ,_m. 'L_,- 3.

PUBLIC SERVICd COMPANY OF COLORADO SR-RE-4-W FORT ST. VF AIN fiUCLEAR GENERATING STATION Issue 4 Page 1 of 10 ATTACHMENT 9 TO P-85040 TITLE: CR0 TEMPERATURE DATA COLLECTION DEPARTMENT: RESULTS ISSUANCE AUTHORIZEDW h W s A

A=

BY PORC / I' EFFECTIVE REVIEW EORC 54 9 DEC 2 71983 OATE 11- %- 9 ~6 Do not start test before Week # and must be completed by Sch. Clerk This procedure cannot be run in its entirety for the following reasons: 1. This system is not operating. 2. This system is not required to be operating and has a frequency of one month or less (reference Technical Specification, paragraph 2.18). 3. Reactor is in " scrammed" condition. 4. Loop I is in " Loop Shutdown" condition. 5. Loop II is in " Loop Shutdown" condition. 6. 1A Helium circulator is in " tripped condition". 7. 1B Helium circulator is in " tripped condition". 8. 1C Helium circulator is in " tripped condition". 9, 10 Helium circulator is in " tripped condition". 10. Other 11. Reschedule test for Departreent Supervisor rom sn.ss.uas y, [VJJ yf Ovvvs /

.. _.. - = _.. .. - - - = _ _ - - - _ - _ _ -.. _.. _. -.. _ _ _._.. = _ PUBLIC SERVICE COMPANY OF COLORADD SR-RE-4-W FORT ST. VRAIN NUCLEAR GENERATING STATION 2 of 10 1.0 pVRp0SE The purpose of this test is to provide for regular temperature recordings of the CRD assemblies that are equipped with temperature devices. 2.0 PRECAUTIONS LIMITATIONS, AND SPECIAL ASSISTANCE None. 3.0 pREREOUISITES 3.1 Test Equipment Last Calibration Name Identification No. Date DVM 3.2 References 4.0 AUTHORIZATIONS 4.1 Departmental Approval Dept. Supervisor Date 4.2 Mech /Elec Clearance Issued, if required: Number Not Required 4.3 Radiation Work Permit Issued, if required: Number Not Required 4.4 Permission to initiate test Shift Supervisor Date PORM 373 33 3443

PUBLIC SERVICE COMPANY OF COLORADO SR-RE-4-W FORT ST. VRAIN NUCLEAR GENERATING STATION Pa 3 of 10 5.0 PROCEDURE 5.1 PRELIMINARY CHECKS 5.1.1 The temperatures are to be read when the reactor power level is 2 50% or the core Ap is 2 3 psid and, a) As soon as possible after weekly control rod drop tests (SR 561.lb-M) have been performed. b) When the reactor steady-state power level is changed 210% or more. This test can be done at the same time that the linear power channels are calibrated because of the change in the power level. 5.2 TEST PROCEDURE (FOR DATA COLLECTION ONLY) 5.2.1 The temperatures to be read are the CR0 motor, orifice valve motor plate and upper helium environment temperatures of the CRO's which have had RTO's (Resistance Temperature Devices) installed in the aforementioned areas. RTO's will eventually be installed in all the CR0 assemblies as the CRO's are pulled out for maintenance and refueling over the next few years. (See data sheets for recording of t6mperatures.) 5.2.2 All temperatures should be less than 250*F, if not, contact Station Manager. Test Conductor Signature Date l ronu m.ss.un

PUBLIC SERVICE COMPANY OF COLORADD SR-RE-4-W FORT ST. VRAIN NUCLEAR GENERATING STATION 4 of 10 DATA SHEET Average Core Reactor POWER Inlet Temp. 'F Primary Coolant Core AP PSIO Flow l l0RIFICE l CRD l l REGION l POSITION l POSITION ll l l(% OPEN) l(INCHES) l I I I 15 l I I 31 1 I I 34 I I l 4 I I l l 5 l l l l 35 l l l l Test Con:uctor Signature Date FORM 373 33 3443

r i [ \\ - rs ll i { SR-RE-4-W lasuo 4 Page 5 or 10 ? t' ?. I DATA SilECT (continued) e Back er HCC Upper llelium Back of HCC Orifice Valve Back or HCC CRD Hotor Temp, l Terminals Envi rosament Terminals Motor Plate Terminals OF per g 0F pe r g or per l g Table M le Table _. Region 15 5 7 1% 6 8 17 4. Region 4 13 6 5 i 14 12 4 Region 34 5 7 14 - l 6 8 17 Region 33 5 7 14 - E 6 8 11 Back of HCC Orifice Valve Back or HCC CRD hotor Terminals Motor Plate Terminals Tempe ra ture CT per

r pe r O

O Table Table i Region 5 7 5 l 35 7 5 8 6 Region 8 6 Is0TE: Reactor Power, Avg. Core inlet Temp.*, Core AP and Primary Coolant Flow f orormation are round on the data logger. Orifice position and CRD position are found on 1-04. Regions 15, 4, 34, 33: resistance reading is converted to *C per Table XVIll. 32 4 C x 9 + 32 = 5 400 1 x 180 + 32 = ' Of Regions 5, 35: Iresistance readino 157 I Test Conductor Signature Dato Il-i a

f PUBLIC SERVICE COMPANY OF COLORADO SR-RE-4-W lssue 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 10 t i 'MEWWWtbWk % " k% bk N:7. } s e ME 5 em m. gal s mm. m m.

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PUBLIC SERVICE COMPANY OF COLCRADO SR-RE-4-W I ' FORT ST. VRAIN NUCLEAR GENERATING STATION g of yg 6.0 TEST CONDUCTOR'S rep 0RT 6.1 Were any procedura changes or deviations made to the test and DCCF/PDR initiated? (Attach copies if applicable) Yes No 6.2 Were all steps successfully completed as stated in test? Yes No 6.3 If the answer to 6.2 is NO, notify Depar+aent Supervisor and list conditions and/or PTR number (s): 6.4 Test completed except for items noted in 6.3 Test Conductor Date 6.5 Test sheets and data sheets reviewed and approved except for items noted in 6.3 Department Representative Date 7.0 DEPARTMENT SUPERVISOR'S/ TEST CONDUCTOR'S REVIEW (If the answer to 6.2 is YES, sections 7.0 and 8.0 are not applicable go to Section 9.0) 7.1 Does the failure described in 6.3 require any action or impose any limit to operation per the applicable LC0(s)? Yes No N/A 7.2 Applicable LC0(s) Action or Limit 7.3 Is the reason test is not being completed at this time due to plant or equipment status? Yes No N/A 7.4 If the ansrer to 7.3 is YES, list condition (s) and/or PTR number (s): 7.5 Is retest necessary for items listed in 6.3 and/or 7.47 Yes No N/A l FORM 372 22 3643

1-PU_~LIC SERVICE COMPANY OF COLORADO SR-RE-4-W FORT ST. VRAIN NUCLEAR GENERATING STATION 10 of 10 l 7.6 If the answer to 7.5 is YES; list specific section(s) or step (s) to be retested. Dept. Supervisor / Test Conductor Date 8.0 RETEST SECTION (If the answer to 7.5 is NO go to Section 9.0) 8.1 Verify satisfactory retest of section(s) or step (s) listed in 7.6 Retest Conductor Date 8.2 Retest reviewed. Department Representative Date 9.0 APPROVALS 9.1 Test results approved. Satisfactory results confirm compliance with applicable LC0(s). Department Supervisor Date 9.2 Notification of satisfactory test results and test conclusion: Shift Supervisor Date 9.3 Requires Station Manager evaluation: Department Supervisor Date 9.4 Station Manager Date 10.0 DATA SHEETS RECEIVED, VERIFIED SECTION 9.0 COMPLETE. AND SURVEILLANCE TEST RECORDS UPDATED. Scheduling Tecnnician Date [ PORM 372 22 3643 -. ---..-. ~ ,- - - -=--- - -}}

ML20106F623

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