ML20154D660
| ML20154D660 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 05/06/1988 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| P-88126, TAC-56126, NUDOCS 8805190286 | |
| Download: ML20154D660 (22) | |
Text
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O Public Service ~
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Company of Colorado 168C5 WCR 19 1/2, Platteville, Colorado 80651 May 6, 1988 Fort St. Vrain Unit No. 1 P-88126 U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Docket No. 50-267
SUBJECT:
Staff Review of the Fort St. Vrain Control Room Design Review Summary Report
REFERENCE:
NRC Letter (G-88079)
Heitner to Williams Dated 03/22/88 Gentlemen:
The purpose of this letter is to provide you with Public Service Company's response to the request contained in Reference 1 for additional information relative to the disposition of human engineering discrepancies (HEDs) 495 and 691.
If you have any questions, please contact M. H. Holmes at (303) 480-6960.
Very truly yours, s0JY JNas~l D. W. Warembourg Manager, Nuclear Engineering Division DWW:DJG/jbl l
Attachments l
cc: Regional Administrator, Region IV l
ATTN: Mr. T. F. Westerman, Chief 03 Projects Section B
}0 Mr. Robert Farrell I \\
Senior Resident Inspector Fort St. Vrain 8805190286 880506 PDR ADOCK 05000267 P
s ATTACHMENT 1 P-88126 Public Service Company's Response to the "REQUEST FOR ADDITIONAL INFORMATION" Relative To Human Engineering Discrepancies (HEDs) 495 & 691 On April 30, 1935, Public Service Company (PSC) submitted a Summary Report (SR) of the Detailed Control Room Design Review (DCRDR) as required by NUREG-0737.
PSC staff members met with the Nuclear Regulatory Commission (NRC) staff in Betnesda, MD, on July 16,
- 1985, to discuss this SR.
An NRC letter dated August 27,1935, (0, R.
Hunter to 0. R. Lee), requested a Supplemental Summary Report and provided minutes of the July 16, 1985 meeting. An included summary listed tne documentation considered "necessary to complete NRC review".
A telephone conference was held between PSC and NRC staff members on September 19, 1985, to clarify these requests.
PSC submitted, by letter dated October 29, 1935, the supplementary information requested by the NRC. Due to the integrated approach to making modifications to panels and resolving Human Engineering Discrepancies (HEDs), PSC has submitted to the NRC, proposed design packages for each separate Danel or panel section where changes will occur, on a schedule corresponding to the completion of each proposed panel redesign.
By letter (P-36005) dated January 17, 1986, PSC requested advance approval of four (4) proposed changes to the Fort St.
Vrain (FSV)
Control Room.
In further discussions witn the NRC staff, these changes were limited to (3) items.
A NRC letter dated June 13,
- 1986, (K. Heitner to R. F. Walker) indicated that the staff had reviewed the three changes and found them acceptable and that PSC could proceed with the implementation.
In addition, a request for specific information relative to thirteen (13) items addressed by various HED's was incluced in tne attached Science Applications International Corporation's (SAIC) Technical Evaluation Report.
PSC suomitted by letter (P-86528) cated August 19, 1956, the specific information requested in the SAIC report.
On July 28, 1937 PSC received a letter (G-87244) which provided Technical Evaluation Reports (TERs) of the remaining design submittals.
These reports reouested additional information, clarification, or justification of certain items addressed by 85 HEDs.
I
ATTACHMENT 1 P-58126 PSC submitted by letter (P-87357) dated October 20, 1937, a response to the request relative to these 35 HEDs.
By letter (P-38066) dated February 10, 1988, PSC requested approval of five (5) changes for implementation durin9 the scheduled circulator outage.
A NRC letter dated March 22,1983 (K. Heitner to R. O. Williams) indicated that these specific changes were acceptable for implementation and requested acditional information relative to HEOs 495 and 691.
This response includes both the SAIC request transmitted by the July 28, 1937, letter (G-37244) and PSC's response to that request as orovided by the letter dated October 20, 1987, (P-87357).
Additional information, (schematics, and functional descriptions) relative to this recent NRC request is provided by this response.
2
ATTACHMENT 1 P-88126 HED-0495 SAIC CCYMENT (Transmitted by letter dated 07/28/87)
"HED-0495 (Category 3) - The discrepancy described is that instrument failure is not apparent to the operators.
Although PSC cites in the disposition that there are other, more direct means of verifying valve function, it appears the instruments used by the operators in the core cooling task analysis (the source of the HED) were those for which failure was not apparent.
PSC should clarify to the NRC which instruments the operators will use for those tasks and whether and how indicator failure can be detected by operators."
SUMMARY
OF PSC's RESPONSE (Transmitted by letter dated 10/20/87)
The source and basis of the HED was clarified.
A description was proviced of each valve function associated with the indicators cited as being center failing.
The response cited the source of the parameter values used to assess system function anc presented the following conclusion:
The presence (or absence) of essential functions are cetermined or verified by a
cynamic performance measure, and not by valve position.
Failure of any component within a particular system, under a "function oriented" approach, requires using the next preferred resource.
Under a "diagnostic approach", valve position indication failure may be determined by simply making a minute control change (via the flow or pressure controller) and checking for an indicated position cnange while verifying a parameter value change.
NRC REQUEST (Transmitted by letter cated 04/22/88)
"HED-495, (Page 36),
involves a
concern about instrumentation failing mic-scale on loss of power.
Does instrumentation in the control room fait mid-scale, and if so, what coes the licensee plan to do to resolve this problem? See NUREG-0700 guideline 6.5.1.1.f."
3
ATTACHMENT 1 P-33126 PSC RESPONSE PSC has resiewed the previous response and continues the position that these ten (10) center f ailing valve position indicators do not provide information essential to either plant operation or safe shutdown, From a system operational
- aspect, tnese indicators may be removed entirely, These indicators do e mvide supplemental information of use during certain maintenance and diagnostic activities, Since these indicators presently exist and have some limited use, it is PSC's intent to maintain this option.
Since these indicators are not required for system operation, neither a mid or left scale failure point will compromise operator actions.
In order to resolve this concern, PSC will change these ten (10) indicators and alter the associated circuitry to provide a left failure position.
This modification will be completed with the I-9305 work effort, CN-1890.
4
ATTACHMENT 1 P-53126 HED-0691 SAIC COMMENT (Transmitted by letter cated 07/28/87)
"HED-0691 (Category 2)
The discrepancies described are i
that '(1) No lamp test method exists, (2) Lamp replacement for Westinghouse Minalites it a problem glass breakage -
bases sticking in holder, (3) Lamp replacement for turbine panel is difficult and bulbs are interchangeable, and (4)
PHC XFER & Reset Button lights difficult to change.'
PSC's resolution for the I-05 components is, ' Bulb replacement aids to be addressed by CN-1900.
Valve and breaker control circuit configuration provide a method by which faulty bulbs are routinely detected and replaced.
Discrete condition indicators are being replaced on all boards with legend indicators wnich havts a test feature.'
PSC snould provide additional information which explains (a) how often (routinely) ooerators are supposed to check for and replace faulty bulbs; and (b) how many of the safety-related indicating lights will not have a means by which they can be detected for malfunction."
PSC RESPONSE (Transmitted by letter dated 10/20/87)
Bulb checks (and replacing faulty bulbs) are routinely orrformed once each work snift in accordance with procedures i
SUAP-4 and 50AP-5.
All safety related indicating lights required for "safe shutdown cooling" will have a means oy whicn they can be verified for functioning.
NRC REQUEST (Transmitted by letter dated 03/22/881 "HED-691, (Pages 43, 55, 61, 69, 76, 82, anc 111), involves a concern regarding indicator lamp failure.
Wnat specific means are proviced to verify tnat safety related indicator lamos are functioning?
See NUREG-0700 guideline 6.5.3.1.a.(2)."
PSC RESPONSE The SAIC comment (letter dated 07/28/87) and the more recent NRC reavest for "additional information" dated 03/22/SS includes references to "safety related" indicating lignts, i
l 5
ATTACHM.ENT 1 P-88126 1
The following clarifications are provided as a basis for further disscusion:
- 1. The Fort St. Vrain Control boards do not contain indicating lights from which an indication is l
required in order to perform a safety related function.
Those indicating lights included within the fuse boundaries of essential circuits within the control room are listed in
}
i PSC's safety related list.
This listing and the corresponcing qualification provides assurance that failure of the component will not comprcmise the essential function.
Thus, the safety related function of these indicating lights is one of maintaining circuit integrity and not one of providing a specific indication.
- 2. The Fort St. Vrain Control boards co not include nor will the exisitng circuit configurations support mass bulb test features.
By standardi ing on indicating light arrays and replacing single discrete indicators with "press to test" holders, PSC has established methocs for detecting faulty bulbs.
general rule, indicating lights installed in the Fort As a St. Vrain Nuclear Generatirg Station Control Room are eitner single discrete indications or are arranged in arrays consisting of two (2) or more individual lamp holders.
Example 1 (see pages 8 & 9) is an example of a single indicator having a means of determining bulb filament integrity.
Those indicating lights appearing in arrays, are connected to snow two (2) or more specific equipment states such as creakers being energized and deenergized or valves being open and closed.
The circuit configuration of these array type arrangements provide a method by which faulty bulbs are routinely cetectec and replaced.
Four (4) specific examples of these circuits configurations are included.
These four examples, 2 tnru 5 (see pages 10 tnru 19) are considered representative of array type arrangements.
Those indicating lights arrangements identified during DCRDR activities as not conforming to the conventions delineated by PSC's Design Directives are being cnanged to conform to these conventions.
6
'TTACkMENT 1 P-88126 I
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l As statec previously, it is PSC's intent to provide or ensure that precedural or physical methods exist, to detect i
i faulty cules for tnose indicating lamps included in safety related circuits, even tnough the indication is in itself not required to perform a safety related function.
Example 6 (see pages 20 and 21) represents a case where an indicating
- light, or it's arrangement or circuit configuration coes not conform to PSC's Design Directives.
Tne function (overload cypass) has been replicated ey the circuit configuration of Example 1 (pages 8 & 9), therefore, 4
tr S bypass circuit, which contains a non-testable bulb will be removed.
I i
l 7
ATTACHMENT 1 P-SS126 EXAMPLE 1 FUNCTICN:
Overload Bypass Initiated SCHEMATIC:
E-1203 P721 (See Page 9)
CONTROLLED DEVICE:
Electrically Energized Relays Maintained position pushbutton, HS-92081 er,ervizes relays CR-92160 & CR-92161.
Contacts of tnese relays provide a bypass circuit around the thermal overloads of certain electrically operated valves.
One set of relay centsets serv 9 to close the circuit to the White light and provides an indication that the "Bypass" function has been selected.
The relay circuit and the white light may be tested by actually performing the function, i
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ATTACHRENT 1 P-SS126 EXAMPLE 2 FUNCTION:
Valve Position Indication SCHEMATIC:
E-1203 PS71 (See Page 11)
CCNTROLLED DEVICE:
Electric Motor Operated Valve, HV-2306 Valve position switch contacts "0V0",
open when the valve is fully opened and contacts "0VC", open when the valve is fully closed.
These c;ntacts provide circuitry to illuminate a green or red Westinghouse Minalite wnen the respective contact is closed by the valve mechanism.
The green light will illuminate at any time the valve (HV-2306) is not fully coen.
This corresponds to the "Close" and "After Close" position (green target) of HS-2306.
The red light will illuminate at any time that HV-2306 is not fully closed.
This corresponds to sne "Open" and "After Open" (ree target) position of HS-2306.
As a result of the above described operation, both lights are illuminated during the valve transient periods ("Af ter Open" or "After Close").
Tnrough training, tne operators recognize that the absence of the illuminated bulb which corresponds to the switch target color, while in static condition warrants checking the bulb filament or replacing the bulb as the first diagnostic activity.
The failure of either bulb to illuminate during the valve transient periods reautres enecKing the non-illuminated bulb filament.
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ATTACHMENT 1 P-OS126 EXAMPLE 3 FUNCTION:
Valve Position Indication SCHEMATIC:
E-1203 522B (See Pages 13 & 14)
CONTROLLED DEVICE:
Pneumatically Operated Valves, HV-21573-1 & HV-21573-2 This example is unicue in that the existing indicating light array coes not meet PSC's Design Directives (DD-ILS-1) convention for valve position indication.
Three lights are configured to indicate the position of two (2) valves.
In addition, this configuration does not provide a convenient means of diagnosing faulty bulbs.
This configuration is subject to change in accordance with CN-18868.
The revised configuration (see pages 14 & 15) is in accordance with PSC's Design Directives and provides a convenient means of diagnosing faulty bulbs.
HS-21573 contacts 3C & 3 (page 13) provide a permissive open for HV-21573-1 in the "Vent" position.
Contacts JC & 4 (page 13) provide a permissive open for HV-21573-2 in the "Normal" position.
Both valves are closed in the "Close" position.
The green light (page 15) will illuminate at any time the valve (HV-21573-1 or HV-21573-2) is not fully open.
The red light (page 15) will illuminate at any time that HV-21573-1 or HV-21573-2 is not fully closed.
The white light will illuminate any time the valve position and the switch position disagree, including during Valve transient periods.
e As a result of the above described operation, three lights are illuminated curing tne valve transient periods.
Through training, the operators recognize that the absence of any one of these three illuminated bulbs during valve transient i
periods, warrants checking the bulb filament or rep'. acing the bulb as the first diagnostic activity.
The absence of either a red or green bulb to illuminate, following the valve transient period requires checking the non-illuminated bulb.
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ATTACHMENT 1 P-88126 EXAMPLE 4 FUNCTION:
Valve Position Indication SCHEMATIC:
E-1203 P449 (See Page 17)
CONTROLLED DEVICE:
Pneumatically Operated Valve, HV-21311 Schematic diagram F449 shows both a three light array and single discrete indications (PAL-21507/8).
A faulty bulb may be readily detected in the thr ee light array, however, a faulty bulb is not easily detected in the case of the single discrete indicators.
Indicators PAL-21507/8 are part of a system which is no longer used and is scheduled for removal.
Valve position switch contacts "0V0",
open when the valve is fully opened and contacts "0VC", open when the valve is fully closed.
These contacts provide circuitry to illuminate a green or red Westinghouse Minalite when the respective contact is closed by the valve mechanism.
The green light will illuminate at any time the valve (HV-21311) is not fully open.
The red light will illuminate at any time that HV-21311 is not fully closed.
The white light will illuminate any time the switch position (HS-21311) differs from the valve position and includes valve transient periods.
As a result of the above described operation, all three lights are illuminated during the valve transient periods.
Through training, the operators recognize that the absence of any one of these three illuminated bulbs during valve transient periods, warrants checking the bulb filament or replacing the bulb as the first diagnostic activity.
The absence of either a red or green bulb to remain illuminated, following the valve transient periods recuires cnecking the non-illuminated bulb filament.
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ATTACHMENT 1 P-88126 EXAMPLE 5 FUNCTION:
Starter Position Indication SCHEMATIC:
E-1203 P311 (See Page 19)
CONTROLLED DEVICE:
480V Starter For Electric Motor Operated Pump P-3309 Starter position switch contacts CR/b, close when the starter is opened (deenergized) and contacts CR/a close when the starter is closed (energized).
These contacts provide the circuitry to illuminate a green or red Westinghouse Minalite.
The green light will illuminate at any time the starter is deenergized.
This corresponds to the "0FF" position of HS-3366.
The red light will illuminate at any time the starter is energized.
This corresponds to the "0N" position of HS-3366.
As a result of the above described operation, one light will be illuminated to correspond to the selected switch position.
The absence of that illuminated bulb which corresponds to the switch position warrants checking the bulb filament or replacing the bulb as the first diagnostic activity.
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ATTACHMENT 1 P-88126 H
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ATTACHMENT 1 P-88126 EXAMPLE 6 FUNCTION:
Overload Bypass Indication SCHEMATIC:
E-1203 P438 (See Page 21).
3 CONTROLLED DEVICE:
Electric Motor Operated Valve, HV-22132 HS-22132-1, a momentary pushbutton is used to bypass the two (2) thermal overload contacts in order to ensure valve HV-22132..
operations under abnormal conditions.
The white light will illuminate when either of the two (2) overload (0.L.) contacts open.
This cues the operator that the thermal 0.L.
contacts have opened and that a manual bypass is i
required to operate HV-22132-1.
This configuration does not conform to PSC's Design Directives for use of white status lights, nor may a faulty bulb be detected in this configuration.
Therefore, a testable legend type light avill be provided.
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