ML20034H696

Provides Response to Request for Info Re Employee Concerns at Plant,Received by NRC

ML20034H696
Person / Time
Site:	Palo Verde
Issue date:	11/06/1992
From:	Conway W ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20034H691	List: ML20034H690 ML20034H696
References
FOIA-92-578 212-01087-WFC-R, 212-1087-WFC-R, NUDOCS 9303190245
Download: ML20034H696 (16)

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Arizona Public Service Company

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-212-01087-WFC/RJS/ACR November 6, 1992

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Mr. John B. Martin Regional Administrator, Region V U. S. Nuclear Reguiatory Commission 1450 Maria Lane. Suite 210 Walnut Creek, Cahfornia 94596-5368

Reference:

LeMer dated September 29,1992, from K. E. Perkins, Jr., USNRC Region V, to W. F. Conway, APS

Dear Mr. Martin:

Palo Verde Nuclear Generating Station (PVNGS)

Subject:

Units 1,2, and 3 Docket Nos. STN 50 528/529/530 Reply to NRC Request for information File: 92-070-026: 92-056-026 The referenced letter requested that Arizona Public Service Company (APS) review information NRC received about employee concerns at PVNGS and provide a response.

Six enclosures were included with the referenced letter, with a separate issue d:scussed in each enclosure. APS' response is provided in the attachment to this letter.

APS has determined that none of the allegations contained in five of the six en0:0sures could be substantiated. In some cases a portion of the alleged facts was found to be correct, but no safety significant matters were identified. Additional time is requ;ted to complete the investigation of the remaining enclosure, Enclosure 4. The response to - provides a current status of the investigation. A complete response to

' will be provided by November 23,1992.

Because the responses to these issues contain personalinformation, the disclosure of which would be an unwarranted invasion of personal privacy. APS requests that the information in this letter and its attachment be considered confidential and with pubhc disclosure pursuant to 10 CFR 9 2.790(a)(6) and 10 CFR 6 9.17(a)(6).

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9303190245 930202 DR-FOIA PNOWICKI92-578 PDR

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12-01087-WFC/RJS/ACR Mr. J. B. Martin U.S. Nuclear Regulatory Commission November 6.1992 Reply to NRC Request for information Page 2 e

The due date for this response was extended from October 29,1992, to November 6, 1

1992, by telephone conference on October 28,1992, between Howard Wong of the NRC, and T. R. Bradish of APS. If you have any questions regarding this letter, please contact Mr. Carter Rogers at (602) 340-4041.

Sincerely, e

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j WFC/RJS/ACR/dmn Attachment - Reply to NRC Request for Information

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J. A. S!can A. C. Gehr A. H. Gutterman NRC Document Control D'esk

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APS RESPONSE TO NRC REQUEST FOR INFORMATION DATED SEPTEMBER 29,1992

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l RESPONSE TO ENCLOSURE 2

i NRC REQUEST l

i Arizona Public Service Company (APS) had not resolved a repetitive.~oblem with a fire I

protection circuit. The circuit which was possibly related to damper control or afarm l

functions to the Unit 2 control room, would open due to overloading of a fuse. System engineers were not too concerned about the problem and were going to ignore it, i

s;2M@h a contract l&C technician, had worked on the fire protection t

circuit in December 1991 and had informed APS managemen and other APS employeegsg?JTd5iQ qand others) of the problem.

NRC Request: As part of the response to this concern APS is also requested to provide g

a list of work order numbers for work performed by in December 1991, t

,I as a result of h. mbers of any CRDRs, nonconformance re along with the n work or as a result of comments made b)M APS RESPONSE T nclosure 2 does not clearly i.dentify a specific Because the information provided i E

problem, APS could not imrnediately identify the condition of concern. As a result, an investigation was initiated to identify the problem or any similar condition.

a First,SMDecember 1991 time billing records were reviewed to determine all work orders tha$ worked on related to the fire protection s stem. These fire protection work orders were then reviewed to determine whether _

or anyone else, identified a condition similar to the one described above. No su conditions were identified, g

Second

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~vas interviewed about the aliegation and was asked i nad ever described a problem similar to the one in Enclosure 2. '

replied that

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did not work on the'two work ~

orders identified in December time records.

Thir the Unit 2 outage l&C foremen of shift (i.e...

were interviewed. The Unit 2 l&C foremen stated that an had never identifie any problem to either of them that was similar to the one described i

in Enclosure 2. The two foremen also reviewed the two December work orders that$

%vorked on and stated they were not aware of any problems involving dampers j

or blown fuses in the circuitry associated with the work orders.

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d Material Non-conformance Fourth, Condition Reports / Disposition Requests (CRDR entified or rep 2ried Reports (MNCRs) were reviewed to determine i did not ;nitiate any any condition similar to that described in Enclosure 2.

CRDRs or MNCRs during December 1991.

Finah, the Plant Engineer responsib!e for fire protection systems was interviewed. The and does not believe Plant Enoineer stated that he had no knowiedge c $

I thcMMarought any plant problem to him. AdditionallyTihe only prob!em even resembkng the problem described in Enclosure 2 was idcntified by an APS technician and the Plant Engineer himself in early 1992.

This problem does involve the fire protection dampers and fuses in the carbon dioxide subsystems. A detailed evaluation of the problem is underway and possible corrective action is being p!anned as part of a Plant Change Request (PCR) package (PCR No. 92-13 FP) presently being processed by PVNGS. This PCR was initiated June 12,1992.

In conclusion, neither the oblem described in Enclosure 2 nor any similar prob em was reported to APS b (p$$Q In response to the NRC's specific request, the work order numbers for work performed byhn@j in December 1991, taken from time records completed bgDQBgj are listed below. As a! ready noted, the search of PVNGS records for December 1991 for

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CRDRs and MNCRs did not identify any initiated bykdMT@$

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I RESPONSE TO ENCLOSURE 3

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NRC REQUESI The annual pedormance of supervisors at Palo Verde was measured in part by the f

number of Condition Report / Disposition Requests (CRDRs) issued against his/her department. In 1991 and 1992,it was expected that no more than three CRDRs were to be issued against the department. This performance system discourages employees from initiating CRDRs.

l APS RESPpQN_SJ The APS performance appraisat system for PVNGS places responsibility and discretion in line management to estab!ish performance targets, measures or goats for employees.

Performance targets for supervisors are established by their direct hne superiors, which at APS are titled Managers. A review of the completed annual performance appraisals S

for PVNGS supervisors for 1991 and 1992 to date revealed no performance targets that utilized the quantity of CRDRs issued against the department as a measure of a supervisor's performance.

q An example target found in PVNGS supervisors' appraisals is:

i EXCELLENCE: Minimizes errors, meets regulatory commitments. Performs quakty work, implements new ways to improve efficiency, maintains individual and staff morale, and supports work rules, j

!n a few instances, a PVNGS Manager described a supervisor's achievement (or l

non-achievement) of excellence in terms of the number of CRDRs that had been is against the supervisor's section during the appraisal period. While APS approves and supports its managers' promotion of excellence, APS is sensitive to the idea that l

performance measures could d:scourage problem identification. As a result, APS will be informing its PVNGS managers and supervisors as part of performance appraisat education, that promotion of excellence, as it relates to or is expressed in CRDRs, should be done by concentrating on the performance or error that led to the CRDR, rather than concentrating on the number of CRDRs written against the section or department. These steps are designed to balance the promotion of excellence with the encouragement of problem identification.

l P

7-

The allegation contained in Enclosure 3 was not substantiated.

There were no pedormance targets or expectations that "no more than three CRDRs" be issued against any department. Notwithstanding the absence of substantiation, APS is taking steps to avoid the possibility of any misunderstanding that would discourage emp!oyees or superviscrs from identifying problems while at the same time continuing to encourage exce)ence.

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RESPONSE TO ENCLOSURE 4 NRC REQUEST l

A ad exceede overtime limits and did no repon a!

inie on the time cards. A rehew of ACAD access records would reveal a mismatch.

APS RESPONSE 3

The Plant Engineering Section of the Site Technical Support Division Mwork group) uses time tickets to determine the hours worked by employees. A time clock is not used, nor are ACAD records reviewed to determine hours worked. Many Piant Engineering personnel have work activities both inside and outside the Protected Area.

.- l ACAD transaction records would not indicate periods of work outside the Protected Area; l

aiso, the ACAD transaction records would not indicate periods inside the Protected Area j

that were spent taking lunch breaks or performing shift turnover. Therefore, ACAD'

', l records are not used to document compliance with PVNGS overtime limitations.

Because the a!!egation in Enclosure 4 indicated that%.ime record and ACAD

.r records did not accurately reflect $ overtime, APS reviewed ACAD_

"i transaction records and time ticket submittals (Payroll Time Cards). The review period.

l selected was from September 22, 1991, to January 22,1992. These records were i

selected because the period began several weeks before the Unit 2 third refueling outage I

and ended several weeks after the completion of that outage. Due to the routine use of.

j overtime during a refueling outage, this period rovides a good basis for determining if

(

overtime limitations were exceeded by j

l A review o f ACAD records an@ime tickets indicated more hours he ACAD records than on the time tickets. When asked to explain this difference stated that the ACAD records included time spent for lunch periods, work breaks, an cther miscellaneous time, such as travel to and from the work place and discussions with coworkers, all whict$did not consider recordable work activites. gtime tickets, therefore, would not reflect those non-work activities.

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. ' d n hiHW M "T e:M'A'ev ar%"tr Mw "-' EaW6Lia;QQ M:1 After initial review, APS has preliminar!!y concluded tha' M has adequately explained the difference betweer[hACAD records and h:s time tickets. As explained above, ACAD records are not useQd4termine overtime limitation compliance. To date, APS' revica has concluded thaQggMd;d wcrk more than 12 consecutive days in vio!ation of PVNGS procedure 02AC-0EM01," Overtime Umitations," whip places a limit on scheduled consecutive work days, in order to determine whethehd!homp!!sd with other PVNGS overtime limits, APS must evaluate whether the time excluced b([4 f

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).s consistent w;th maa,agement's expectations and the intent of the PVNGS ovemme I;m tation procedure.

APS' review and eva' vat:on w;H be comp eted by November 23, 1992, and the results wi:1 be provided to the NRC in a supplemental response. Apprcpriate corrective measures are betng eva'uated and w!'l be discussed in APS'supp emental response.

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RESPONSE TO ENCLOSURE 5 r

NRC REQUEST The steam line supplying AFP-P01, the turbine driven auxiliary feedwater pump, has a smail amount of steam flow to keep the turbine warm to prevent overspeed. As a resuit, the steam line should be reclassified as a high energy line rather than a passive line.

Note: Region V understands this steam line is not classified as a high energy line in the Pa!o Verde FSAR: however, Region V has learned that Palo Verde operates with the isolation valves for the steam line slightly open and this practice might affect the classification of the line.

L' APS RESPONSE Palo Verde operates with valves SG UV-134 and 138 in the fully closed position (torque seated MOVs), but allows a small amount of leakage (normal seat leakage due to wear)

I to warm the steam supply lines for the Auxiliary Feedwater Pump Turbine for the Palo Verde Units. The temperature of the steam is approximately 212F and the pressure is essentiatly atmospheric. The temperature of the line is monitored to be within 190F to 212F. Since there is little stored energy in the line, the Auxiliary Feedwater Pump steam supply line does not meet the Branch Technical Position APCSB 3-1 and MEB 3-1 definition of a high energy steam line.

The design and classification of these steam lines have been evaluated by APS and reviewed by the NRC on several occasions. In each case, these evaluations have confirmed that during normal plant conditions, the Auxiliary Feedwater Pump steam supply lines are notin operation and are not pressurized. The only time these steam lines are pressurized is when the steam driven Auxiliary Feedwater Pumps are in operation, a condition that occurs less that 2% of the plant cperating time. On that basis, f

the NRC has accepted the PVNGS design relative to the Branch Technical Positions. This acceptance is documented in Section 10.4.9.2.C of the PVNGS Safety Evaluation Report.

The classification of the steam supply line was raised, whh the NRC present, in the Independent Design Review held in Phoenix on August 21 and 22,1980. The transcript of this meeting is on the Palo Verde docket. More recently, the classification of the steam line was raised during a telephone conversation with NRR regarding EER 90-SG 172 in September 1990 and again in a discussion with Region V as noted in Inspection Report 50-528/91 31 Consistently, Palo Verde has taken the position that the steam supply lines

{

from valves SG-UV-134,134A,138 and 138A to the Auxiliary Feedwater Pumps are not high energy lines.

11-

The amount of grease in motor operated valve operators is regularly checked during preventative maintenance inspections.

The procedure, 39MT 92202, *PM/EOPM inspection of the GL 8910 Limitorque SMB/SB Valve Motor Operators," requires inspection of both the quantity, quality, and consistency of the grease in the Main Housing Cavity. If the amount of grease is not proper, add;tional grease must be added.

This program has notidentified a significant problem with grease levels in motor operated l

valves.

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