ML20247F964

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Documents 890711 Telcon Between CP Patel, J Bongarra & Author Re Deferral of Certain Dcrdr Commitments.Conversation Directed to Three Specific Issues & Related Human Engineering Deficiencies
ML20247F964
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 09/11/1989
From: Trzyna G
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 8909180330
Download: ML20247F964 (23)


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l-Commonwealth Edison 72 West Adams Street, Chicago, Illinois A3 dress Reply to: Post Office Box 767~

Chicago. Illinois 60690 - 0767 September 11, 1989 Director of Nuclear Reactor Regulation US Nuclear Regulatory Commission Mail Station P1-137 ATTN: DOCUMENT CONTROL DESK Hashington, DC 20555

Subject:

Zion Nuclear Power Station, Units 1 and 2 License Nos. DPR-39 and DPR-48 NRC Docket Nos. 50-295 and 50-304 Status of D_CRDR Commitments Reh rence:

July 11, 1989 telephone conversation between C.P. Patel/J. Bongarra (NRR) and Commonwealth Edison Personnel Gentlemen:

The purpose of this letter is to document a July 11, 1989 telephone conversation between G. Trzyna et al., and C.P. Patel/J. Bongarra regarding the deferral of certain Detailed Design Control Room Review (DCRDR) commit-ments.

The nature of the conversation was directed to three specific issues and their related Human Engineering Deficiencies (HED).

The three issues are:

1) The redesign of the Chemical and Volume Control System (CVCS) control board mimic; 2) the nuisance alarms caused by the Aircraft Crash Detection System; and 3) the replacement of the recorders associated with the installed Radiation Monitoring System.

The Commonwealth Edison representatives in attendance for the conference call were:

G. Trzyna, R. Landrum. C. Greaves, R. Lane, J. Rodhe, L. Peterson (DCRDR Coordinator-Contractor).

l The discussion of each of the items is presented below.

1)

CICS_ConirnLharDJtdesign The original DCRDR and associated HED's, indicated a necessity to realign the control board (CB07) instrumentation as it relates to the CVCS in order to improve the mimic for that system.

This original conceptual design was developed with the understanding that the optimization of the mimic may be constrained by the actual amount of space on the control board.

This spatial limitation provided for an improved mimic design for the letdown portion of the CVCS, and only partial improvements to the charging portion of the CVCS.

Attachment 1 is a one line diagram of the CVCS. Attachment 2 indicates the existing configuration of CB07; and Attachment 3 provides the rearrangement that resulted from the original design of the mimic.

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September 11,1989L Subsequent to.the original submittal, and unknown to the DCRDR personnel,'other CECO resources were pursuing certain plant L

modifications which would remove the Boron Injection Tank-(BIT) and change the concentration of boric acid in the Boric Acid Storage

. Tanks (BAT) from 12% to 4% by weight. The control board affect of these modifications would result in increased space on panel CB07 because several valve operators will no longer be required and can l

consequently be removed.

When the DCRDR personnel were made aware of these proposed modifica-tions, they then suggested that the CVCS

. mimic be reconfigure to optimize the charging portion of the CVCS. provides the optimum design of the mimic for both portions of the CVCS.

Commonwealth Edison feels that a deferral of the implementation of the CVCS mimic in order to provide an optimum design is justified by the importance of the instrumentation under. normal, abnormal and emergency conditions.

For your review, the original ten HED's related to the CVCS are contained in Attachment 5.

An appraisal of the affect of this deferral is provided in the paragraph entitled

" Evaluation of the Impact of Deferral" which has been added to each of the original-HED's.

Commonwealth Edison also believes that the frequency of changes to the physical placement of the controls on the main control board should be minimized and accomplished in a manner that ensures safe operation by minimizing confusion to the control; board operator.

Therefore, Commonwealth Edison suggests that the deferral is prudent because it provides a more meaningful rearrangement of control board controls consistent with the intention of DCRDR requirements and that intermediate attempts to rearrange the control board rather than one complete effort would only serve to confuse the control room operator.

The proposed implementation dates are Spring, 1991 Refueling Outage for Unit 1; and the Fall, 1991 Refueling Outage for Unit 2.

2)

A_ttgraft Crash DetettlDDLhi_sance Alam This item refers to an HED associated with a Control Room annunciator that is frequently in " alarm" and has been regarded as a nuisance alarm.

The alarm function of this annunciator is driven by varied and multiple signals, one input of which is that from the aircraft crash detection system.

The proposed corrective action to the elimination of this portion of the nuisance alarm was to address the concern through a Technical Specification amendment, supported by an engineering evaluation, to allow us to conclude to that the aircraft crash system was not required, and could therefore be removed from Technical Specifications.

Removal of the system from the Technical Specifications wculd allow the Station to remove the aircraft crash detection signal from the alarm input and thereby eliminate the nuisance alarm.

This item was not extensively discussed during the phone call, however, a commitment was made to submit the proposed Tech Spec to the NRC by July 18, 1989.

The proposed amendment was submitted to the NRC on July 18, 1989.

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1, Dir. of NRR.

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. September 11, 1989 i-3)

Recorders for Radiation Monitorina SyJLtem Zion Station has been addressing the deficiencies associated with the recorders that are used with.the. installed Radiation Monitoring System for.a number of years. As a result of the DCRDR effort, four specific HEDs were initiated that applied to both Units 1 and 2.

A modification was originated to correct the HEDs and was completed'for Unit 1 and partially completed for Unit 2.

However, a human factors evaluation.of this modification indicated that the newly installed recorders on both units may have addressed the original HEDs, however, they also created new HEDs.

This_ situation halted a continuation of the modification for Unit 2. contains the January 23, 1989 letter which provides more details of the event.

Specifically discussed in the July 11, 1989, telephone conversation was the issue of chart eligibility of the multi-point recorders.

This inadequacy of the recorder is related to the physical dimensions of the recorder, i.e.., the smaller the size of the recorder the greater the difficulty to read the data points.

The problem is further complicated by the physical space available to mount the recorders on the back of the main control boards for.each respective Unit. Unit 2 control board panels have more space to install larger recorders than Unit I control board panels because Unit I contains unit-specific and common radiation monitoring equipment.

Therefore, two different solutions to the problem must be developed.

The Unit 2 problem is easier to correct and will be addressed by March, 1990, prior to the second refueling outage.

However, because of spatial limitations on the Unit 1 panel, a different model of recorder must be employed.

This decision will be made In sufficient time to ensure that the new Unit I recorders will.be installed by March, 1991.

For your review, the original four HEDs related to the Radiation Monitoring System are contained in Attachment 7.

An appraisal of these HED's that are affected by the proposed deferral is provided in a paragraph amended to the original HED entitled " Evaluation of the Impact of Deferral."

If there are any further questions regarding this matter, please contact this office.

Very truly yours, p

G. E. Trzyna Nuclear Licensing Administrator scl/im 0283T:1-3 cc: Chandu Patel-NRR Senior Resident Inspector-Zion W/o Attachments

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i a jp ~_3; .n m o,.. - i ,*L, . _ ; Ia,. puna j -w m .o ~ .!? Oa-I;h ' d ' _ [fr) f. l; .e ~ ? ZION NUCLEAR POWEP STATION DETAILED CONJ 33L ROOM DESIGN REVIEW ATTACHMENT 5 QRIGifLALEBQ7_1tED's AND AN EVALUAUQN OF TRE IMPACT OF DEEERML l 1 I /st1:0283T:19 . _ _ _ - _ _ _ _ _ ~ Zion Corrective Action 1 1 .HED N0.: 0157. 0169 j GUIDELINE: fLRC.1-2. 9.1.2. B 2-1 2 l CATEGORY: 2 LEVEL B flHDitEl The controls and displays for the volume control tank (VCT) are not grouppd together or well laid out on CB07. (Photo Log No. D-26, 36) RESE0HSIl The cited VCT instrumentation will be rearranged to provide a functional grouping. EVALUA_ HON OF IMPACT OF DEEIERAL These HED's identify that controls and displays for the VCT are not grouped together or well laid out on CB07. They were identified as CATEGORY 2, LEVEL B indicating that they are associated with plant systems that are not related to engineered safeguard systems or engineered safety features and only have a moderate influence on plant performance which may delay or impact, but not significantly, the efficient operation of the plant. IMPLEMENTATl0_N_1 By the completion of the second refueling outage. /sc1:0283T:6 .~ s Zion Corrective Action HED NO.: RLL4 GUIDELINE: fL2AA-1 CATEGORY: 2 LFVEL B flHQ1HG1 There are sixteen groups of display / control strings which are not in a logical left-to-right, top-to-bottom order based on alphabetical sequence. (Photo Log No. E-10 through 24, G-19). RESP._0NSE1 N The electrical bus, diesel generator IB, diesel generator ventilation fan, and fire annunciator components are arranged in the same order as they are arranged in the plant. The Steam bypass, boron injection tank, volume control tank, residual heat removal, heating system, and isolation valve controls will be swapped to result in an alphabetical arrangement. The points on the reactor coolant pump recorders will be changed so that one recorder contains points A and B and the other contains points C and D. EVALUATION OF IMPACT OF DEFERRAL This HED identified 16 groups of displays on various panels that are not in a logical left-to-right, top-to-bottom order based on alphabetical sequence. Four of these groups of displays would be unresolved if the CB07 work is deferred. They were identified as CATEGORY 2, LEVEL B indicating moderate, but no significant impact on the efficient operation of the plant. JHP_. EMENTall0H1 L By the completion of the second refueling outage. /sc1:0283T:7 l o j. Zion Corrective Action l HED No.: Q132. 0413. 0156. 032.9 GUIDELINE: H.1.1. ALQS-1. 8.1.1. A/VR-3. 8 J.1.C.1-1. 8. 3.2&J LQS-2 CATEGORY: 2 LEVEL.__B _ i E1HDlNG1 l l The following system valve controls (on CB07) are not optimally grouped:

1) Makeup injection to volume control tank valve FCV-VC111B
2) Boric acid injection to blender valve FCV-VC111A
3) Primary water injection to blender valve FCV-VC111A
4) Makeup injection to charging pump header valve FCV-VC110B 5)

Reactor coolant makeup control

6) Reactor coolant makeup control
7) Boric acid
8) Primary water
9) FCV-110A controller These controls are operated in sequence and are not functionally groupad.

(Photo Log No. D-35) RESE0HSfl The meters will be rearranged to result in a functional grouping. In addition, enhancements (background shading, demarcation, and mimics) will be added to CB07. EVALUAURN OF IMPACT OF DffERilAl These HED's identified that several valve controls on CB07 are not optimally grouped. They were identified as CATEGROY 2, LEVEL B indicating moderate, but not significant impact on the efficient operation of the plant. IMPLEMENTATIQH1 By the completion of the second refueling outage. /sc1:0283T:8 ~ i Zion Corrective Action HED NO.: Q335 l GUIDELINE: 8.1.1. BIOS-10 l CATEGORY: 1 LEVEL 3 E1EnlRG: The operaters reported that the layout of the following systems is confusing.

1) Chemical Volume and Control System (CVCS) and accumulators (on CB07)
2) Test line valves for emergency core cooling (on CB10) 3)

Emergency core cooling (on CB08, CB09, CB10)

4) Residual heat removal (on C608) l
5) Safety injection (on CB10)

RESEONSfa The meters for CVCS will be rearranged to result in a functional grouping. Enhancements (background, shading, demarcation and mimics) will be added to CB08, CB09 and CB10 to clarify groupings of the other cited instrumentation. IYALUAILON OF IMPACT OLEEERBA_L This HED identified that the layout of several systems was confusing as identified in an operator survey. They systems identified were CVCS, i accumulators, ECCS test valves, ECCS, RHR and SI. They were identified as CATEGORY 1, LEVEL B indicating that there were discrepancies associated with engineered safeguards systems or engineered safety features with moderate, but not significant impact on the efficient operation of the plant. The l rearrangement of those systems that are related to engineered safeguards systems will not be impacted by this deferral. The CVCS system valve controls are not considered engineered safeguards. IMPLiMEE18110li By the completion of the second refueling outage. /scl:0283T:9 u_-_-___ t o o IION CORRECT 1VE ACT10N HED NO : '115-GUIDELINE: 8.2.1.C.1/VL-13 CATEGORY: 1 LEVEL B f1N.DJ1G: On several occasions during the validation, operators were observed attempting to restore / control pressurizer level with the charging and letdown systems and leaving the systems (on CB07) to observe pressurizer level (on CB06). RESE0HSI: A pressurizer level meter will be added to CB07 above the charging / letdown controls. LyALUATION OF IMPACT OF DEFERIML This HED identified that operators were leaving hte CB07 panel to monitor pressurizer level on CB06 when controlling / restoring pressurizer level with the CVCS valves. This HED was identified as CATEGORY 1, LEVEL B indicating that it affected an engineered safeguards system with moderate, but not significant impact on the efficient operation of the plant. The category identified is due to the fact that this HED addresses pressurizer level. The tasks associated with restoration of the CVCS system and controlling pressurizer level are not directly related to a safeguards function. If the letdown system has isolated, and it is being unisolated, leaving it isolated for a longer period of time is conservative since charging is maintained at all times and pressurizer level will be increasing, This verification of pressurizer level prior to restoring letdown by observing indication of CB06.would not have significant impact. The volume of the pressurizer is large enough that operating without letdown will not result in reaching solid plant conditions for several hours. Therefore any time required to check pressurizer level would be insignificant in comparison. Additionally, a computer trend recorder exists on CB07 which allows operators to select pressurizer level if desired. IMPLEMENTATION: By the completion of the second refueling outage. /scl:0283T:10 T d ZION CORRECTIVE ACTION HED NO.: 03B3 GUIDELINE: L h (103-2 CATEGORY: 3 LEVEL C ELNDjj[G: The reactor coolant pump seal and bearing outlet temperature meters (on CB07) have confusing labels. The " bearing inlet" is the " bearing outlet" on plant diagrams. Switch position of the seal and bearing temperature meters do not reflect the order of flow.

RESPONSE

The cited level will be reengraved " bearing outlet".

The seal and bearing temperature meters will be switched to reflect the order of flow.

LYALUATION OF IMPACT OF DEFERRAL:

This HED identified that the indication for reactor coolant pump seal and bearing outlet temperatures had confusing labels and their relative positions do not reflect the order of flow.

This HED was identified as CATEGORY 3, LEVEL C indicating that it has relatively minimal impact on plant l

performance, The interim corrective measure to correct the problem with the confusing labels has been corrected.

IMPLEMENTATION:

By the completion of the second refueling outage.

/scl:0283T:ll

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HON _HU. CLEAR POWER STATION DEBILED_CQHIRQL ROOM DESIGN REVIEW AUACHMEEL6 LANUARY 23. 1989 LETTER REGaBD1HG_SlAIUS_QE_860BII0B M01UDE_R_EC0EDIRS l

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