ML20035G854
| ML20035G854 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/14/1993 |
| From: | Merschoff E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Skolds J SOUTH CAROLINA ELECTRIC & GAS CO. |
| References | |
| NUDOCS 9304300114 | |
| Download: ML20035G854 (22) | |
Text
^
APR 141993 e t gh
\\\\),t?
Docket No.:
50-395 (f
License No.: NPF-12 South Carolina Electric & Gas Company ATTN: Mr. John L. Skolds Vice President Nuclear Operations V. C. Summer Nuclear Station P. O. Box 88 Jenkinsville, SC 29065 Gentlemen:
SUBJECT:
MEETING
SUMMARY
- SUMMER This refers to the meeting conducted at your request at the NRC Region II Office in Atlanta, Georgia on April 6,1993. The purpose of the meeting was to discuss several NRC proposed violations identified at Summer's Nuclear Plant during recent MOV, EDSFI, and Resident Inspector inspections.
The licensee presented its position and supporting information on these matters as identified in Enclosure 2.
It is our opinion that the meeting was beneficial in that it provided us with a better understanding of the licensee's programs in the subject areas, concerns, and views on these issues.
l I
Should you have any questions concerning this letter, please let us know.
Sincerely, Original signed by:
Ellis W. Merschoff i
Ellis W. Merschoff, Director r
Division of Reactor Projects
Enclosures:
1.
List of Attendees 2.
Summer /NRC Meeting Handouts cc w/encls:
R. J. White Nuclear Coordinator S.C. Public Service Authority Virgil C. Summer Nuclear Station P. O. Box 88 (Mail Code 802)
Jenkinsville, SC 29065 i
(cc w/encls cont'd - See page 2) 9304300i14 930414 I
PDR ADOCK 05000395 G
PDR ZE0l \\
4 F
APR I 41993 South Carolina Electric & Gas Company 2 4
(cc w/encls cont'd)
G. J. Taylor, General Manager Nuclear Plant Operations South Carolina Electric & Gas Co.
Virgil C. Summer Nuclear Station P. O. Box 88 (Mail Code 300) 1 Jenkinsville, SC 29065 i
J. B. Knotts, Jr., Esq.
Winston and Strawn 1400 L Street, NW Washington, D. C.
20005-3502 Chairman i
Fairfield County Council i
P. O. Drawer 60 l
Winnsboro, SC 29180 Heyward G. Shealy, Chief Bureau of Radiological Health S. C. Department of Health i
and Environmental Control 2600 Bull Street Columbia, SC 29201 Mr. R. M. Fowlkes, Manager Nuclear Licensing and Operating Experience South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station P. O. Box 88 i
Jenkinsville, SC 29065 bcc w/encls.
G. F. Wunder, NRR F. Cantrell, RII S. Vias, RII Document Control Desk i
NRC Resident Inspector U.S. Nuclear Regulatory Commission Route 1, Box 64 Jenkinsville, SC 29065
{
- SEE PREVIOUS CONCURRENCE RII:DRP RII:DRP RII:DRP RII:DRS
- RWright:tj
- FCantrell
- DVerrelli
- JCaudle 04/ /93 04/ /93 04/ /93 04/ /93 l
l I
l-u APR I 41993 South Carolina Electric & Gas Company 2 l
t (cc w/encls cont'd)
G. J. Taylor, General Manager Nuclear Plant Operations i
South Carolina Electric & Gas Co.
Virgil C. Summer Nuclear Station P. O. Box 88 (Mail Code 300) i Jenkinsville, SC 29065 J. B. Knotts, Jr., Esq.
Winston and Strawn 1400 L Street, NW Washington, D. C.
20005-3502 Chairman i
Fairfield County Council P. O. Drawer 60 Winnsboro, SC 29180 Heyward G. Shealy, Chief l
Bureau of Radiological Health S. C. Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 Mr. R. M. Fowlkes, Manager Nuclear Licensing and Operating Experience South Carolina Electric & Gas Company
?
i l
Virgil C. Summer Nuclear Station l
P. O. Box 88 l
Jenkinsville, SC 29065
-i i
bcc w/encls:
G. F. Wunder, NRR F. Cantrell, RII S. Vias, RII Document Control Desk J
NRC Resident Inspector
]
U.S. Nuclear Regulatory Commission Route 1, Box 64 l
Jenkinsville, SC 29065 r
}
RII:DRP RII:DRP RII:DRP k
II:DRS R.Jd, ;
j
@V
-O V
RWright:tj FCantrell DVerrelli FMMe 04/9/93 04/ /93 04/ W 93 04/ /93 1
i l
I ENCL _0S!)RE 1 l
1 NRC Attendees i
C. A. Julian, Chief, Engineering Branch, Division of Reactor Safety (DRS),
i Region II, (RII) i M. B. Branch, Acting Chief, Test Programs Section, DRS, RII F. Jape, Acting Technical Assistant, DRS, RII M. D. Hunt, Reactor Inspector, Test Programs Section, DRS, RII M. N. Miller, Reactor Inspector, Test Programs Section, DRS, RII P. J. Fillion, Reactor Inspector, Plant Systems Section, DRS, RII D. M. Verrelli, Chief, Reactor Projects Branch 1, Division of Reactor Projects
- i (DRP), RII F. S. Cantrell, Chief, Projects Section 1B, DRP, RII l
R. W. Wright, Project Engineer, Projects Section IB, DRP, RII i
L. A. Keller, Resident Inspector, Projects Section 1B, DRP, RII G. F. Wunder, Project Manager, Project Directorate II-I, Office of Nuclear l
Reactor Regulation Licensee Attendees D. A. Lavigne, General Manager, Nuclear Safety R. M. Fowlkes, Manager, Nuclear Licensing and Operations Experience 1
i f
I i
t t
1 i
i h
i I
e.,r
ENCLOSURE 2 i
NRC PRESENTATION ON PROPOSED VIOLATIONS FOR VIRGIL C. SUMMER NUCLEAR STATION j
i l
i i
APRIL 6,1993 1
l t
REGION ll ATLANTA, GEORGIA i
i t
D. A. LAVIGNE R. M. FOWLKES a
THREE PROPOSED VIOLATIONS 1.
MOTOR OPERATED VALVE TEST ACCEPTANCE CRITERIA 1
II.
DRAWING ERROR FOR ELECTRICAL BREAKER DATA i
Ill.
BREACH OF TEMPORARY CONTAINMENTPENETRATION DURING CORE ALTERATION i
.+
/
)
i MOV PROGRAM ES-EVALUATE APPLICATIONS-PROVIDE:
VALVE LIST, TEST CONDITIONS, SWITCH SETTING RECOMMENDATIONS 5.1.3.A
- 6 S
- 1 I VALVES TO BE TESTED)
I I II
) (
l PLANNING AND SCHEDULING
' SWITCH SETTINGS TEST CONDITIONS MOV REFURBISHMENT, SETSWITCHES. PERFORM STATIC i
TEST 5.2
- 6.3.2*
STATIC TEST NO
/ \\
SATISFACTORY YES
) g DP TEST 6.3.4
- s ELEC. MAINT.-VLV/ OPERATOR DATA TEST GROUP-SYSTEM DATA 1 f 1f 1 f
/
\\
SYSTEM DATA STATIC TEST DATA VALVE / OPERATOR DATA 1f 1
ES-CONFIRM TEST DATA j
y.
i r
1I l
l
') f J
VALVE FUNCTIONED NO OWAN RELEASE VALVE LAW EMP 445.012 FOR REALIGNMENT /
j (-
SYSTEM OPERATION l
?N MODES 3,4,5 & b YES l
1 f i
l TEST DATA VAllDATED NO BY MOVCOORDINATOR l
ER PTP-270.XX
,j i
1 f YES DESIGN ENGINEERING IMPLEMENTATION I
OF TRACKING AND TRENDING PROGRAM PROCEDURE TEXT REFERENCE
i ELECTRICAL MAINTENANCE PROCEDURE EMP-445.008 l
MOTOR OPERATED VALVE DATA i
i e
CONTAINS THE DESIGN BASES THRUST VALUES FOR j
MOVS.
1 e
MINIMUM THRUST VALUES ESTABLISHED BASED
~
ON DESIGN BASES ANALYZED DIFFERENTIAL PRESSURE.
e PROCEDURE PROVIDES INFORMATION AS INPUTTO OTHER TEST PROCEDURES - CONTAINS NO -
ACCEPTANCE CRITERIA.
i i
.y EMP-445.008 ENCLOSURE 10.1 PAGE 7 OF 13 REVISION 5 l
MOTOR OPERATED VALVE DATA STROEE OVERALL VALVE ID MCC ELEMENTARY FLA TYPE /SIXE MIM MIN MAX
- ggg, MAXIMUM OPEN CIDSE l
XVG03103A XMCIDA2X 14AD 208-101-SW23 2.8 SMB00
< 75 13522 14000 16219 14000 XVG03103B XMCIDB2Y 18AD 208-101-SW24 2.8 SMB00
<75 13522 14000 16381 14000 XVG03107A XHCIDA2X 14EH 208-101-SW27 2.8 SMB00
<75 13522 14000 16211 14000 XVG03107B XMCIDB2Y 18EH 208-101-SW28 2.8 SMB00
<75 13522 14000 16385 14000 XVG03108A XMCIDA2Y 161H 208-101 SW29 2.3 SMB00
< 50 7138 7719 13048 14000 XVG03108B XHCIDA2Y 15CG 208-101-SW30 2.3 SMB00
< 50 7138 7719 13072 14000 XVG03108C XHCIDB2Y 181H 208-101-SW31 2.3 SMB00
< 50 7138 7719 13340 14000 XVG03108D XHCIDB2Y 191M 208-101-SW32 2.3 SMB00
< 50 7138 7719 13340 14000 XVG03109A XMCIDA2Y 15HL 208-101-SW33 2.3 SMB00
< 50 7138 7719 13171 14000 XVG031098 XMCIDA2Y 14CG 2080-101-SW34 2.3 SMB00
< 50 7138 7719 13072 14000 XVG03109C XMCIDB2Y 20IM 208-101-SW35 2.3 SMB00
< 50 7138 7719 13337 14000 XVG03109D XMCIDB2Y 211M 208-101-SW36 2.3 SMB00
<50 7138 7719 13346 14000 XVG03111A XMCIDA2X 13EH 208-101-SW39 2.3 SMB00
<62 7648 8819 12852 14000 XVG03111B XMCIDB2Y 19EH 208-101-SW40 2.3 SMB00
< 62 7648 8819 12754 14000 XVG03112A XMCIDB2Y 20EH 208-101-SW41 2.3 SMB00
<62 8234 8819 12872 14000 XVG031128 XMCIDA2Y 16EH 208-101-SW42 2.3 SMB00
< 62 8234 8819 12548 14000
...w....
ELECTRICAL MAINTENANCE PROCEDURE EMP-445.011 j
BASELINE TESTING OF LIMITORQUE VALVES WITH THE MOVAT 3000 SYSTEM e
PROVIDES FOR THE STATIC SETUP AND TESTING OF THE VALVE OPERATORS.
e COMPARES DEVELOPED THRUST OR ADJUSTED TOTALTHRUSTWITH THE MINIMUM AND MAXIMUM LIMITS PROVIDED FROM THE VALVE DATA PROCEDURE.
e ACCEPTANCE CRITERIA 15 THAT THE VALVE
=~
OPERATOR DEVELOPS THRUST IN THE REQUIRED RANGE.
e PROVIDES ASSURANCE THAT THE DEVELOPED THRUST IS WITHIN THE CAPABILITY OF THE OPERATOR TO FUNCTION UNDER DESIGN BASES DIFFERENTIAL PRESSURE CONDITIONS.
i
ELECTRICAL MAINTENANCE PROCEDURE t
i EMP-445.012 DIFFERENTIAL PRESSURE TESTING OF l
LIMITORQUE VALVES e
ESTABLISHES TEST EQUIPMENT SETUP AND DATA COLLECTION FOR MONITORING VALVE OPERATOR PERFORMANCE DURING DIFFERENTIAL PRESSURE i
TESTING.
e SYSTEM ALIGNMENT AND OPERATION IS
)
ADDRESSED FOR EACH SYSTEM TO BE TESTED IN A DIFFERENT SERIES OF PROCEDURES.
i e
ACCEPTANCE CRITERIA:
RESULTS OFTESTING AND ANALYSIS HAVE 1
VERIFIED THAT THE VALVE WILL OPEN AND CLOSE l
FULLY AGAINST DIFFERENTIAL PRESSURE (DEVELOPED BY THE SYSTEM).
PROCEDURE ALSO RECORDS THRUST REQUIRED TO o
OVERCOME DIFFERENTIAL PRESSURE.
b
PREVENTIVE TEST PROCEDURE PTP-270.XXX DP TESTING OF (VARIOUS MOTOR OPERATED VALVES) e PROCEDURES ESTABLISHES THE PHYSICAL SETUP OF THE PLANT I
SYSTEM TO ALLOW THE PERFORMANCE OF THE DIFFERENTIAL PRESSURE TEST FOR THE MOTOR OPERATED VALVES IN THE SYSTEM.
e THIS TEST IDENTIFIES THE EXPECTED DIFFERENTIAL PRESSURES TO BE DEVELOPED BY THE SYSTEM BASED ON DESIGN CALCULATIONS.
l 0
THE PROCEDURE RECORDS THE ACTUAL DIFFERENTIAL PRESSURE ACHIEVED DURING THE TEST.
j i
e ACCEPTANCE CRITERIA-1)
VALVE COMPLETES FULL STROKE IN BOTH OPEN AND CLOSED -
DIRECTIONS AS VERIFIED BY POSITION INDICATION LIGHTS ORE l
DIAGNOST!C DP TEST SIGNATURES.
i 1
2)
MEETS THE ACCEPTANCE CRITERIA OF EMP-445.012.
3)
VALIDATION OFTEST CRITERIA:
DIFFERENTIAL PRESSURE AND FLOW DEVELOPED ACROSS THE VALVE SHALL BE EVALUATED BY THE MOV COORDINATOR TO DETERMINE IF THE TEST IS ACCEPTABLE PER THE MOV j
PROGRAM.
J i
~
I PROPOSED VIOLATION FOR INADEQUATE ACCEPTANCE CRITERIA 1)
EMP-445.011," BASELINE TESTING OF LIMITORQUE-VALVES WITH MOVATS 3000 SYSTEM" LISTED NO DATA FOR THE REVIEWER TO BASE ACCEPTANCE.
RESPONSE
PAGE 5 OF 6 ATTACHMENT 1 RECORDS MINIMUM AND MAXIMUM THRUSTS
^
PROM EMP-445.008," MOTOR OPERATED VALVE DATA," IDENTIFIES THE DEVELOPED THRUST IN BOTH THE OPEN AND CLOSED DIRECTION, DETERMINES THE ADJUSTED TOTAL THRUST.
l THE PROCEDURE INTENT IS TO VERIFY THAT THE' ADJUSTED TOTAL THRUST FALLS WITHIN THE RANGE OF THE REQUIRED MINIMUM AND-MAXIMUM.
3 IF IT DOES NOT, A NON-CONFORMANCE NOTICE-15 GENERATED TO EVALUATE THE FAILURE.
h 4
t-
-W-w r
y 5
2)
EMF-445.012," DIFFERENTIAL PRESSURE TESTING OF LIMITORQUE VALVES" i
THERE IS NO VALUE GIVEN FOR WHAT l
DIFFERENTIAL PRESSURE MUST BE MET OR WHERE 3
THE REQUIRED PRESSURE IS TO BE OBTAINED.
RESPONSE
THE DIFFERENTIAL PRESSURE WHICH MUST BE MET IS THAT DIFFERENTIAL PRESSURE DEVELOPED BY THE SYSTEM AS SPECIFIED IN i
THE PREVENTIVE TEST PROCEDURE. IF THE VALVE STROKES FULLY IN BOTH THE OPEN AND i
CLOSED DIRECTIONS AGAINST DIFcERENTIAL PRESSURE, THEN THE ACCEPTANCE CRITERIA OF:
THIS PROCEDURE HAS BEEN MET.
)
o
.c i
3 1
i
3)
PTP-270.XXX,"DP TESTING OF(VARIOUS MOTOR OPERATED VALVES)"
i THERE IS NO REQUIREMENT THAT FLOW SHUT OFF BE VERIFIED.
RESPONSE
THE VERIFICATION THAT THE VALVE 15 ~
POSITIONED BY STATUS LIGHTS OR BY DIAGNOSTIC TEST SIGNATURE IS ACCEPTED INDUSTRY PRACTICE.
THE VALVE LIMIT SWITCHES HAVE BEEN PREVIOUSLY VERIFIED BY THE STATIC SETUP PROCEDURE. THERE IS NO TECHNICAL BASES TO QUESTION THEIR ACCURACY.
t
?
i
The overall issue is whether or not the validation of the test differential pressure against design bases number is required to be in the procedure as an acceptance criteria.
Violation refers to 10 CFR 50, Appendix B, Criterion V, " Test Procedures May incorporate or Reference the l
Requirements and Acceptance Limits contained in Applicable Design l
Documents."
l i
i
=e----ee w
a m.
~
e-
_--y-m g
The PTP 270 series procedures reference
)
the appropriate design documents for minimum required thrust and DP calculations. In addition, Enclosure 10.2 identifies the expected design DP values.
i The MOV Coordinator is knowledgeable
{
of these documents and is fully capable of comparing the test differential pressure to the calculated design i
differential pressure to determine test validity. This evaluation is a requirement specified in the acceptance criteria of the PTP-270 series procedure.
~
PROPOSED VIOLATION FOR DRAWING ERROR INSPECTION REPORT 93-10 i
e INVOLVED A CHANGE TO MAGNETIC ADJUSTABLE TRIP RANGE VALUE FOR A BREAKER FOR A CONTROL ROOM EMERGENCY VENTILATION FAN.
e THE CORRECT RANGE WAS PROVIDED ON THE APPROVED DRAWING. THE INCORRECT RANGE WHICH WAS TO BE REPLACED WAS NOT DELETED FROM THE DRAWING.
THE DRAWING 15 A CONTROLLED NON-ESSENTIAL DRAWING. IT IS NOT UTILIZED BY PLANT MAINTENANCE PERSONNEL TO SET THE BREAKER TRIP SETTINGS.
e THIS WAS VERIFIED AS THE ONLY ERROR IN APPROXIMATELY 240 CHANGES MADE BASED ON PLANT WALKDOWNS.
)
e THERE IS NO SAFETY SIGNIFICANCE RELATED TO THIS DRAWING ERROR.
LOAD DESCRIPTION LOAD DATA STARTER DATA BREAKER DATA 1-LIMITER T
EQUIPMENT NO. SYSTEM LOAD SIZE TYPE TRIP (A)
TRIP (A)
NAMEPLATE ENGRAVING FULL LOAD (A)
SIZE CATALOG NO.
CATALOG Nt LOCK ROTOR (A)
HEATER ADJ. TRIP RANGE TEST VALUI.
SERVICE FACTOR ACTUAL SET (A)
TRIP TIME 40 XVB9524B - CC 1.00 HP R
S
(' COMP. COOLING WATER TO 1
FHL36015-13M
(
B0.92 50-150 IH
_XVB9525A- --
( COMP. COOLING WATER TO 1
FHL36015-13M
( NON-ESS EQUIP. LOOP _ A B0.92 50-150
%+
XVG9606
- - CC
.33 HP R
IL (COMP. COOLING WTR RTN
.80 1
FHL36015-13M
( FROM RB ORC 5.30 Bl.ls 50-150 1.00 4
,XVB95038- -- --
FHL36015-13M EXCH B B0.92 50-150
[F XFN00418 AH 5.00 HP NR COMPUTER ROOM 1
FHL36015-13H SUPPLY FAN B B10.20 50-150 (UNIT D GH XFN0036B AH 15.00 HP NR RELAY ROOM 2
FHL36030-15M SUPPLY FAN B B32 100-300 (UNIT D
- IM XVT80968 RC
.66 HP R
20 REACTOR HEAD VENT VV 1
FHL36015-13M IFL34020l TO PRESSURIZER B2.85 50-150 60 RELIEF TANK (100 SEC.
lA ES BLANK
- BD XFN0028B AH 50.00 HP NR CONTROLLED ACCESS 60.00 3
FHL36100-1BM EXHAUST FAN B 340.00 CC87.7 300-1100 1.00
IIM ES BLANK 12A0
.XVB9503B-- - - --
FHL36015-13M
( EXCH B B0.92 50-150 12EF XFN00418 AH 5.00 HP NR COMPUTER ROOM 1
FHL36015-13M SUPPLY FAN B B10.20 50-150 (UNIT D 12GH XFN0036B AH 15.00 HP NR RELAY ROOM 2
FHL36030-15M SUPPLY FAN B B32 100-300 (UNIT D 121H XVT80968 RC
.66 HP R
+
REACTOR HEAD VENT VV 1
FHL36015-13M TO PRESSURIZER 82.65 50-150 RELIEF TANK 13A ES BLANK 1380 XFN00288 AH 50.00 HP NR rJ CONTROLLED ACCESS 60.00 3
FHL36100-18M EXHAUST FAN B 340.00 CC87.7 300-1100 1.00
~
13EG XFN0030B AH 40.00 HP NR CONTROL ROOM EMERG 52.00 3
FHL36100-18M FILTERING SYST FAN B 384.00 CC74.6 300-1100 1.00 275-1000 13H1 ES RELAY COMPARTMENT 13JM XVG3005B SP 0.7 HP R
FHL36015-13M ISOLATION 11.90 B2.65 50-150 e
E,
~
PROPOSED VIOLATION FOR FAILURE TO MEET CONTAINMENT CONDITIONS REQUIRED BY TECHNICAL SPECIFICATION 3.9.4 - INSPECTION REPORT 93-09 e
MINOR BREACH OF TEMPORARY PENETRATION SEAL DURING CORE ALTERATION ACTIVITIES.
e ENGINEERING EVALUATION DETERMINED PENETRATION SEAL (DEGRADED) WAS CAPABLE OF PERFORMING ITS DESIGN FUNCTION AS A FIRE BARRIER AND TO LIMIT ANY DESIGN BASES RADIATION RELEASE TO A SMALL FRACTION OF ACCEPTABLE LIMITS.
e LICENSEE NEEDS TO UNDERSTAND WHAT THE ALLOWABLE REGULATORY LEAKAGE LIMITS ARE IN MODE 6 FOR A SEALED PENETRATION.
e WE DO NOT BELIEVE THAT ZERO LEAKAGE IS REASONABLE OR EXPECTED.
i 3
REFUELING OPERATIONS 3/4.9.4 REACTOR BUILDING PENETRATIONS l
LIMITING CONDITION FOR OPERATION P
W 3.9.4 The reactor building penetrations shall be in the following status:
a.
The equipment door closed and held in place by a minimum of four
- bolts, b.
A minimum of one door in each airlock is closed, and c.
Each penetration providing direct access from the reactor building atmosphere to the outside atmosphere shall be either:
1.
Closed by an isolation valve, blind flange, or manual valve, or 2.
Be capable of being closed by an OPERABLE automatic Reactor r
Building Purge and Exhaust isolation valve.
6 APPLICABILITY:
During CORE ALTERATIONS or movement of irradiated fuel within l
the reactor building.
ACTION:
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the reactor building.
l SURVEILLANCE REQUIREMENTS t
4.9.4 Each of the above required reactor building penetrations shall be 3
determined to be either in its closed / isolated condition or capable of being closed by an OPERABLE automatic Reactor Building Purge and Exhaust isolation E
valve within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement o' irradiated fuel in the reactor building by:
a.
Verifying the penetrations are in their closed / isolated condition, or b.
Testing the Reactor Building Purge and Exhaust isolation valves per the applicable portions of Specification 4.6.4.2.
]
i SUMMER - UNIT 1 3/4 9-4
\\