ML17251A940
| ML17251A940 | |
| Person / Time | |
|---|---|
| Site: | Ginna |
| Issue date: | 02/17/1988 |
| From: | Bettenhausen L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Snow B ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| NUDOCS 8802250116 | |
| Download: ML17251A940 (32) | |
Text
REGULA RY INFORMATION DISTRIBUTI SYSTEM (RIDS>
ACCESSION NBR: 8802250116 DOC. DATE: 88/02/17 NOTARIZED:
NO DOCKET FACIL: 50-244 Robert Emmet Ginna Nuclear Planti Unit 1s Rochester G
05000244 AUTH. NAME AUTHOR AFFILIATION BETTENHAUSENi L.
Region ii Ofc of the Director RECIP. NAME RECIPIENT AFFILIATION SNOWI B. A.
Rochester Gas 5 Electric Corp.
SUBJECT:
Discusses 880211 management meeting. List of meeting attendees h vieujgraphs of dc fuse evaluation program encl.
DISTRIBUTION CODE:
IEABD COPIES RECEIVED: LTR l ENCL +
SIZE:
TITLE: Summary of Significant Meeting with Licensee (Part 50>
NOTES License Exp date in accordance tui th 10CFR2> 2. 109(9/19/72>.
05000244 RECIPIENT ID CODE/NAME PD}-3 L*
INTERNAL: AEOD/DOA DEDRO NRR/DREP/EPB10D OGC/ROED RES/DE/EIB EXTERNAL:
LPDR NSIC COPIES LTTR ENCL 1
0 1
1 1
1 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME STAHLE. C AEOD/DSP/TPAB NRR/DLPG/GAB10A NRRJ&5AS/ ILRB12 EG FQ 02 1
FILE 01 NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 1
1 1
1 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 15 ENCL 14
PEB 1g )988 Docket No. 50-244 Rochester Gas and Electric Corporation ATTN:
Mr. Bruce A.
Snow Superintendent Nuclear Production 49 East Avenue Rochester, New York 14649 Gentlemen:
Subject:
February ll, 1988 Management Meeting This refers to the February 11, 1988 management
- meeting, held in our mutual in-
- terest, in the Region I office (see Enclosure 1 for attendees).
We appreciate your interest in keeping us informed of your progress and plans for resolution of DC fuse anomaly.
Matters discussed during this meeting included your technical approach to develop-ing and maintaining design bases for DC fuses and the DC distribution system and the status of resolution of anomalies identified in the course of your evaluations.
You also described progress and plans during the present refueling outage to com-plete walkdown inspections, verify existing fuses, to make fuse changes in accord-ance with the design basis as equipment is available in the outage, and to resolve all previously identified anomalies except one involving ¹12 transformer lockout relays which will not 'be available during the outage and which you have evaluated as a change desired to meet newly developed technical
- bases, but not necessary for proper functioning.
You then provided a status of refueling outage work.
NRC announced its intention to conduct a team inspection of outage activities the week of February 22, 1988 and solicited your assistance in obtaining inspection preparation information.
Thank you for your cooperation and your information input.
We look forward to other informational meetings.
Sincerely, Lee H. Bettenhausen, Chief Projects Branch No.
1 Division of Reactor Projects
Enclosures:
1.
Meeting Attendees 2.
Viewgraphs of DC Fuse Evaluation Program
~gag 8802250i16 880217 PDR ADOCK 05000244 P
PDR OFFICIAL RECORD COPY 24/BETTENHAUSEN/2/12/88 - 0001.0.0 02/12/88
Rochester Gas and Electric Corporation 2
FEB 17 19M cc w/encls:
Harry H. Voigt, Esquire Central Records (4 copies)
- Director, Power Division Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector State of New York bcc w/encl:
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o encl)
DRP Section Chief Robert J.
- Bores, DRSS RI:DRP ettenhausen/meo 2/1g/88 OFFICIAL RECORD COPY 24/BETTENHAUSEN/2/12/88 0002.0.0 02/12/88
ENCLOSURE 1
MEETING ATTENDEES FEBRUARY 11.
1988 Rochester Gas and Electric Com an Robert W. Eliasz, Nuclear Engineer George S. Link, Manager, Electrical Design Julie Loria, Electrical Engineer Robert C. Mecredy, Director, Engineering Services Jane Neis, Liaison Engineer Robert E. Smith, Chief Engineer Bruce A. Snow, Superintendent, Nuclear Production Nuclear Re ulator Commission Re ion I W. Baunack, Project Engineer, Division of Reactor Projects (DRP)
Lee H. Bettenhausen, Chief, Projects Branch No.
1, DRP Jacque Durr, Chief, Engineering Branch, Division of Reactor Safety (DRS)
Thomas
- Koshy, Lead Reactor
- Engineer, DRS Ralph J. Paolino, Acting Chief, Plant Systems
- Section, DRS Jack R. Strosnider, Chief, Materials and Processes
- Section, DRS OFFICIAL RECORD COPY 24/BETTENHAUSEN/2/12/88 0003.0. 0 02/12/88
TECHNICAL
SUMMARY
DC FUSE EVALUATION PROGRAM o
Objectives o
Criteria o
Design Analyses o
Design Example o
Results:
Original System Proposed Changes o
Internal Audit o
Conclusion
DC FUSE EVALUATION PROGRAM EWR 334l OBJECTIVE:
Establish a fuse design basis for use on the two Class lE DC distribution systems and assess the adequacy of the original design.
Specific review objectives included:
0 Veri fy that fuses associated with Class lE loads are adequately
- sized, rated and coordinated for all design basis ev'ent 0
Verify.that the fuses provide the required isolation of Non Class 1E loads.
Verify adequate overload and short circuit protec-tion on all branch circuits.
0 Establish configuration control documentation.
o Establish a fuse testing program.
A system Design Criteria was developed using current requirements applicable to coordination.
A summary of the two most significant standards applicable to Ginna are shown along with correspon-ding design approaches.
o GDC-17:
CAPACITY AND CAPABILITY TO PERFORM SAFETY FUNCTIONS DESIGN')
All "End of Line" (EOL) fuses are sized assuming all components are operating con-currently.
This represent the maximum credible load.
b)
All sub branch fuses supplying a group of discrete EOL fu es (i.e. in MCC, Buses, Relay Racks, etc.)
are also sized a suming all loads (class 3 E and Non 1E) operating concurrently.
(No Diversification!)
c)
All main fuses supplying subbranches are sized to carry all Class 1E maximum credible load current plus 125% of normal load for all Non Class 1E loads.
d)
The effects of voltage regulation>
accident temperature conditions and cable ampacity limits are accounted for in each fuse applica-tion.
o IEEE STD 308:
CONNECTION OF NON CLASS lE LOADS TO AND FROM CLASS lE DISTRIBUTION BUSES DESIGN a)
Fuses supplying non Class 1E loads provide isolation so that Class 1E loads are not rendered inoperable due to a fault on a
Non Class 1E load.
b)
Fuses supplying Class lE loads are coordinated with upstream fuses to preclude loss of other loads.
c)
The loading effects of non faulted loads are included in the isolation analysis to insure adequate isolation and coordination.
DESIGN ANALYSES:
The following analyses demonstrate that specific objectives are satisfied.
o CABLE AMPACITY:
The purpose is to:
a)
Establish the maximum continuous current value (ampacities) for all cable types using manu-facturers recommendations or NEC.
b)
Establish the maximum fuse size for each cable size and configuration to ensure long term protection.
o DC SYSTEM LOAD SURVEY:
The purpose is to:
a)
Establi h current values for all DC components based on manufacturer's information.
b)
Tabulate "End of the Line" (EOL) maximum credible load currents for lE and Non 1E components.
c)
Combine all EOL maximum credible loads on each system to size subbranch main fuses.
d)
Tabulate total maximum credible current and normal current values for each system.
e)
Determine main branch fuse sizes.
o DC FUSE COORDINATION:
The purpose is to:
a)
Apply fuse ampere ratio criteria to main/branch fuse combination which is later confirmed on a subsequent analysi b)
Derate fuse rating for temperature and to tabulate "capacity margin ratios".
(i.e.
"aerated fuse rating" divided by the "maximum credible load current").
c)
Determine fuse size and type for each appli-cation using results of other analyses.
d)
Establish criteria for DC motor starters.
o VOLTAGE REGULATION STUDY:
The purpose is to develop voltage drop calculations for each branch circuit and ensure adequate sy tern voltages under wor t case operating conditions.
The voltage drop calculations included the following assumptions:
a)
Naximum credible load current was assumed on each circuit.
b)
Battery Chargers Inoperable c)
Cable Temperature 70oC d)
Ambient Temperature
~0oC Zn addition>
a more severe set of calculations was performed that was used to derate cables.
The assumptions associated with this study included:
a)
The assumed currents in each branch was the largest fuse size allowed by the Ampacity Analy is.
b)
Cable Operating Temperature 90oC c)
Chargers Operating
o FUSE ISOLATION AND COORDINATION.
'The purpose of this analysis is to verify that the ampere ratio criteria, developed by the manu-facturer<
provides the required isolation.
The loading effects of unfaulted circuits were con-sidered.
This analysi a)
Ensures coordination between main and branch fuses assuming loading effects.
b)
Demonstrates isolation of Non Class lE loads prior to loss of any safety related load and without damage to upstream fuse.
c)
Develops maximum fuse total clearing and damaging characteristics.
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SYSTEM LOAD SORVBY Distribution or Control Panel:
lA BATTERY MAIN FUSE CABINET Drawing Numbers:
10909-36 Total Normal Load:
126.92A Total Max imum Emerg ency Load:
404. 32A (1E Max
+ 1.25 x non-lE Norm)
Pos.
Device 1A BATT CHRGR Max Load NA Oper.
Time (sec)
Normal Load(A)
Load 1E 2
MAIN DC DIST.
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RESULTS:
The following is a summary of the general condition of the original system and some of the proposed changes:
ORIGINAL SYSTEM DESIGN:
a)
Approximately 2000 fuses are inservice on the two Class 1E DC systems consisting of 25 various types (many with identical charac-teristics).
b)
Fuses feeding Class 1E loads had adequate capacity.
Capacity margins ratios
> l.
c)
Fuses associated with non Class 1E load were pro perl y isolated using good engineer ing practice.
d)
Branch circuits were originally designed to account for long cable runs.
Normal voltage regulation
(
3 percent.,
PROPOSED CHANGES:
a)
Replace approximately 800 fuses to reduce the number of fuse types to 9.
b)
Change the main fuse type to improve coordi-nation.
c)
Class lE Fuse Size Changes Upsize fuses on 17 circuits to improve coordination.
2)
Down ize 20 circuits (with unnecessarily high capacity margins) to improve coordina-tion or voltage regulation.
d)
Non Class 1E Fuse Size Changes Upsize fuses on three circuits to en ure operability without sacrificing isolation.
2)
Downsize fuses on 11 circuits to improve isolation and/or coordination.
INTERNAL AUDIT.
An internal technical audit assessment was performed by QA and T
D Division Engineers not associated with the design effort.
The results suggested that:
A clarification of the source for specific component current values be included in the Design Analysis.
The manufacturer'ecommended fuse sizes on breaker close coils be evaluated for adequacy.
o Tabulated load data sheets be arithmetically rechecked and corrected if necessary.
o Provide additional uppoi t for some analytical assumptions.
AUDIT RESPONSE:
o Clarification provided on Analyses.
Breaker close coils were evaluated and the supply fuse was found 'to be adequate.
0 Load data sheets corrected with no impact on fuse sizing.
0 Analytical assumptions checked and no changes to fuse size found necessary.
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CONCLUSION:
The DC Fuse Evaluation program a) provided a
means for demonstrating coordination by ensuring both capacity and isolation reauirements are sati fied.
b)
Demonstrated the adeauacy of branch circuitry.
c) provided technical fuse data to enable configu-ration control to be maintained.
d) provided a
means to track and a sess the impact of additional loads.
e)
Implemented a batch lot fuse testing program.
PRIORITY CLASSIFICATION NO ANAMOLY*
TOTAL ANAMOLIES 52 124 16 199 NUMBER RESOLVED 39 83 16 142 NUMBER REMAINING OPEN 13
>>0>>
57 Priorit Level Descri tion Potential detrimental effect on 1E bus or Safety Function.
Potential challenge to/from non safety system or reduced margin to 1E system.
No challenge to equipment.
Re>>verif ications determined no Anamoly.
1988 OUTAGE PLANS Previously identified Anamolies Exception:
512 Transformer Lockout Relays 150 2
~
Size Changes Due to EWR Evaluation 56 3
~
Type Changes 200 4
~
Additional Walkdowns 3 remaining panels not inspected at power
- wiring inspection on remaining D.C. distribution systems (to extent practical) 5.
Verification of existing fuses Plant personnel walkdown QC surveillance on installation QA audit review
1988 OUTAGE 7
10 CIRCUIT REPLACEMENTS PER DAY (AVG.)
Bus 13 Outage Bus 14 Outage Bus 16 Outage Bus 15 Outage Bus 17/18 2-7-88 (1 day) 2-10-88 (2 day) 2-13-88 (2 day) 2-21-88 (1 day)
Per Component Basis
ADMINISTRATIVE CONTROLS A-60, Control of DC Systems Fuse Size
& Coordination D.C. Reference Manual Maintenance Procedures Material Controls
- Other Administrative Procedures (e. g. Holding Rules, Jumper Control)
- Periodic QC Surveillance
PRIORITY CLASSIFICATION NO ANAMOLY*
TOTAL ANAMOLIES 52 124 16 199 NUMBER RESOLVED 39 83 16 142 NUMBER REMAINING OPEN 13 41 57 Priorit Level Descri tion Potential detrimental effect on lE bus or Safety Function.
Potential challenge to/from non sa fety system or reduced margin to 1E system.
No challenge to equipment.
Re-verifications determined no Anamoly.
1988 OUTAGE PLANS Previously Zdentified Anamolies Exception:
412 Transformer Lockout Relays 150 2.
Size Changes Due to EWR Evaluation 56 3.
Type Changes 200 4
~
Additional Walkdowns 3 remaining panels not inspected at power
- wiring inspection on remaining D.C. distribution systems (to extent practical)
~ ~
5.
Verification of existing fuses Plant personnel walkdown QC surveillance on installation QA audit review
1988 OUTAGE 7
10 CIRCUIT REPLACEMENTS PER DAY (AVG.)
Bus 13 Outage Bus 14 Outage Bus 16 Outage Bus 15 Outage Bus 17/18 2-7-88 (1 day) 2-10-88 (2 day) 2-13-88 (2 day) 2-21-88 (1 day)
Per Component Basis
ADMINISTRATIVE CONTROLS
- A-60, Control of DC Systems Fuse Size
& Coordination
- D.C. Reference Manual Maintenance Procedures Material Controls
- Other Administrative Procedures (e.g.
Holding Rules, Jumper Control)
Periodic QC Surveillance