ML20235V675
| ML20235V675 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/09/1987 |
| From: | Silver H Office of Nuclear Reactor Regulation |
| To: | Wilgus W FLORIDA POWER CORP. |
| References | |
| NUDOCS 8710150264 | |
| Download: ML20235V675 (9) | |
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a UNITED STATES g
h NUCLEAR REGULATORY COMMISSION
,j WASHINGTON, D, C. 20655 U
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October 9, 1987 Docket No. 50-302 Mr. W. S. Wilgus Vice President, Nuclear Operations Florida Power Corporation ATTN: Manager, Nuclear Licensing P.O. Box 219 j
Crystal River, Florida 3?629 1
1 I
Dear Mr. Wilgus:
SUBJECT:
AUDIT OF THE CRYSTAL RIVER, UNIT-3, DETAILED CONTROL ROOM DESIGN REVIEW ann SAFETY PARAMETER DISPLAY SYSTEM DESIGN j
i As previously discussed with members of your staff, the Human Factors Assessment Branch and its consultants, Science Applications International Corporation (SAIC), plan to conduct an audit of Florida Power Company's (FPC's1 l
- progress on conducting a Detailed Control Room Design Review (DCRDR) and of i
the design of the Safety Parameter Display System (SPDS) for Crystal River,
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Unit 3.
The audit team vill evaluate the organization, process, and results i
of FPC's DCRDR and SPDS efforts. The audit is planned for October 19-23, 1987 at Crystal River Unit 3.
Please make the following preparations:
t 1.
Review team personnel (including contractors) knowledgeable in each of the DCRDR and SPDS tasks should be available to discuss the review process and to respond to staff questions during the audit.
L 2.
Up-to-date documentation of the organization, process, and results of the DCRDR and SPDS efforts should be available.
i 3.
Conference or office space should be available for the NRC staff's meeting with FPC and for the staff and its consultants to meet privately.
4.
Access to the control room, simulator, and remote shutdown facilities should be provided as necessary.
Escorted access will be acceptable.
5.
Clearance to bring camera equipment on-site and to take photographs in the control room and other areas that would assist in evaluating the DCRDR and SPDS efforts should be provided, hogy h p
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October 9,1987 Mr. W. S. Wilgus We plan to conduct the DCRDR audit from October 19-21, with a DCRDR closeout briefing on Wednesday morning. The SPDS audit will begin on Wednesday afternoon and be completed on Friday morning with an SPDS exit briefing.
In order to assist the licensee in preparing for the on-site audits, we are providing the following enclosures:
1.
A proposed DCRDR audit agenda.
l 2.
A list of DCRDR human engineering observation (HE01 concerns.
3.
A proposed SPDS audit agenda.
4.
Names, affiliations, and Social Security numbers of review team personnel. This enclosure is provided to assist in positive identification of team members.
It is not being placed in the Public Document Rooms.
Please be prepared to address and provide us documentation required for each of the items identifed in the enclosures.
Sincerely,
'f I
Harley S 1 er, Project Manager Project rectorate II-2 Division of Reactor Projects-I/II
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Enclosures:
As stated k
cc w/o enclosure 4:
See next page i
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Li Octobei-9, 1987
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N Mr.LW. S. Wilgus
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r e
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- We~ plan to conduct the DCRDR audit from October 19-21, with a DCRDR closeout-
.. briefing on_ Wednesday morning. The SPDS' audit Will 'begin on Wednesday Eafternoon and be completed on Friday morning with.an SPDS exit briefing.
In orderL to assist the licensee in preparing for the on-site audits, we are provi. ding the-following enclosures:
l' 1.
.A proposed DCRDR audit agenda.
2.
A list of DCRDR human engineering observation (HE0) concerns.
3.
A' proposed SPDS. audit agenda.-
- 4..
Names, affiliations, and Social Security numbers of review team personnel.
This' enclosure is provided to. assist in positive identification of team members.
It is not being placed in the Public Document Rooms.
'Pl' ease.be prepared to address and provide us documentation required for each of the items identifed in the enclosures.
. Sincerely,
/s l
/
Harley Silver, Project Manager l
Project Directorate II-2
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Division of Reactor Projects-I/II 4
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Enclosures:
.As-stated j
i cc w/o enclosure 4:
i See next page DISTRIBUTION
- w/o enclosure 4:
19ectatgpew.
HBerkow.
d NRC & Local PDRs HSilver PD22 Reading OGC-Bethesda SVarga EJordan Glainas JPartlow a
-DMiller ACRS (10)
Gray File l:. :P I-2 D:P6Q:2 D
er HSilver:bd HBerkow 10/. /87,
10/c /87 10/]/87 i
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i
y Mr-$W2S..Wilgus.
Crystal River Unit No. 3 Nuclear
.Flo'rida Power Corporation
' Generating Plant i
CC:'
Mr. R. W; Neiser State Planning and Development
' Senior Vice President 1 Clearinghouse and General Counsel Office of Planning and Budget Florida Power Corporation.
Executive Office of the Governor
.P._0. Box 1404?
The Capitol. Building St. Petersburg, Florida 33733 Tallahassee, Florida 32301' Mr. P. F. McKee Mr. F. Alex Griffin, Chairman Director, Nuclear Plant Operations Board of County Commissioners 1
- Florida. Power Corporation
' Citrus County P. O. Box 219 110 North Apopka Avenue
<s Crystal River, Florida 32629 Inverness, Florida 36?50 Mr. Robert-B. Rorsum Mr. E. C. Simpson Babcock A Wilcox Director, Nuclear Site
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Nuclear Power Generation Division Florida Power Corporation Support Suite 220, 7910 Woodmont Avenue P.O. Box 719 Bethesda, Maryland 20814 Crystal River, Florida 3?6?P Resident Inspector U.S. Nuclear. Regulatory Commission 15760 Wcst Powerline Street Crystal River, Florida 3269.9 Regional Administrator, Region 11 U.S. Nuclear Regulatory Comission 101 Marietta Street N.W., Suite 2900 4
Atlanta, Georgia 303?3 Jacob Daniel'Nash Office of Radiation Control Department of Health and Rehabilitative Services
,i 1317 Winewood Blvd.
l Tallahassee, Florida 32399-0700 Admini stra tor l
Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road
-Tallahassee, Florida 32301 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304
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l ENCLOSURE 1 i
Tentative Pre-Implementation Audit Agenda i
for Crystal River Nuclear Plant, Unit 3 1
I October 19-21, 1987 I
Day 1 1:00 p.m.
Introduction of the NRC Audit Team
-Brief Presentation on the DCRDR program by the licensee l
-Discussion of individual elements and activities of the DCRDR program 1:30 p.m.
SystemFunctionandTaskAnalysis(SFTA) Discussion a.
Discuss how the generic Abnormal Transient Response
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h1 Guidelines were converted to the upgraded plant specific j
emergency operating procedures.
b.
Discuss how the SFTA identified a comprehensive set of operator tasks for emergency operations at CR3.
c.
Discuss how the necessary operator information and control requirements along with instrumentation and control characteristics were identified.
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4 d.
Discuss how the tasks identified during the task analysis.
I would cover operator tasks during a loss of integrated -
control system event.
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i Presentation on individual elements and activities of the DCRDRprogram(continued) 8:30 am Assessment of HEOs a.
Provide a detailed description of the assessment process, specifically on the method for estimating the safety consequence and the potential for error associated with the HE0s.
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b.
Provide clarifications on the method used for prioritizing HEOs, including those that have a low safety significance but high potential for error.
c.
Provide the audit team with sample assessment documentation for review.
I 1:00 p.m.-
Selection of Design Improvements
-Provide clarifications or resolutions for HEOs concerns identified in Enclosure 2 of this letter.
Day 3 8:30 a.m.
Sample survey of the control room conducted by the NRC audit team 10:00 a.m.
Comparison of audit team's finding with the Licensee's DCRDR team findings.
11:00 a.m.
DCRDR exit briefing.
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1 ENCLOSURE 2 List of HE0 Concerns
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HE0 No.
Page*
Connents 0062 56 Bailey controllers do not have, engineering.
units.
0063 57 Bailey controllers do not have engineering units. Clarify the statement " Depending on n
the mode of operation of these controls, the scale of the meters may have more than one,
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meaning."
0154 75 It appears that zone banding may provide.
additional-help in identifying the required range.
0161 78 Low pressure injection system is usually considered as a safety-related system.
Please clarify the statement "LP flow and DH controls are not safety related..."
0261 90 This HE0 does not relate to " glare" problem, l'
The justification provided seems to be inappropriate.
i' 0245 179 Apparently, this problem has occurred before.
j-Since the MSIV controls could trip the plant if they were in a wrong position, providing i
resistance in the control knob should be more appropriate.
0229 211 If the operator must control pressure within plus or minus 15 psi, then changing the gauge scale from 20 psi increments to 25 psi increments is inappropriate. The licensee should review this proposed corrective action.
0379 216 The HE0 indicated that throttle valve should not be throttled based on B&W recommendation.
However, the FPC's corrective action is to replace valves with throttleable valves.
Please clarify this discrepancy.
- Page numbers as found in the licensee supplemental summary report (SSR) dated September 30, 1986.
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9 ENCLOSURE 3 Tentative Agenda for Post-Implementation Audit of Crystal River 3 Safety Parameter Display System (SPDS)
October 21-22, 1987 DAY I 1:00 p.m.
Overview of SPDS Implementation (Presentations by Licensee) a.
Definition of SPDS b.
Parameter Selection Process c.
Human Factors Engineering Program d.
Reliability e.
Verification and Validation Program f.
Implementation Program g.
Project Milestones 2:30 p.m.
Critical Safety Function / Parameter Selection (Presentations by Licensee) a.
Parameter Selection e.
b.
Critical Safety Functions (Vs. NUREG-0737)
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c.
Critical Safety Functions / Parameter Relationships d.
Range of Events / Conditions covered by paraseters e
e.
H.F. Safety Evaluation Concerns 8
3:30 p.m.
SystemDesign(Presentations,byLicensee) a.
System Description
b.
Display Configuration c.
Data Validity e.
Security System Verification and Validation (Presentations by Licensee) l a.
Verification Test Plan b.
Validation c.
Maintenance & Configuration Control i
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i TENTATIVEAGENDA'(Continued)
I 4:30-p.m.
Discussion /p1hningfor:next' day i
5:30 p.m.
Adjourn w'
DAY 2 i
m 8:30 a.m.
HumanFactorsEnsinteringReview(ControlRoom) a.
Display Locatioit y
b.
Display Fomtt c.
Display Techniques b.
Open Concerns N
CperationsReview(ControlRoom)
I d.
Ccncise Display t'.
Parameters identified in SAR on SPDS
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c.
Critical,SSfety Functions (0737 and Plant) d.
Reliability (Hardware / Software)
- e.. Response Yimes (Display Call-up and Screen Update) f.
Integrated into Emergency Operations g.
SPDSParameterValues.vs.FixedPanelValues(Comparison) i h.
Procedures and Training i
1.
Control Room SPDS vs. Simulator SPDS comparison l
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ElectricalIsolattsn
,l 12:00 Lunch*
o, 1:00 p.m.
Operatom Interviews 5
- a. ' Shift Supervisor i
- b., Reactor OperatoN.'1 1
c.' Shift Technical Advisori
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Dor.omentatiun'Re iew, 3 4 3:30 p.m.
Audit Team Caucus y
4:00 p.m.
Discussion ivith Licensee on results of Audit DAY 3 8:30 a.m.
SPDS Exit Briefinh.
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