ML20041G374
| ML20041G374 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 02/22/1982 |
| From: | Robert Lewis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20041G362 | List: |
| References | |
| NUDOCS 8203220155 | |
| Download: ML20041G374 (16) | |
Text
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,g NUCLEAR REGULATORY CC'311SSION ATTACH'1ENT 2
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.s 101 MARIETTA ST.. N.w, st. -I :100
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0, ATLANTA, GEORGI A 3C-03
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FEB 2 21982 SSIris 50-395 i
MEMORANDUM FOR:
D. G. Eisenhut, Director, Division of Licensing, Office of Nuclear Reactor Regulation R. C. Lewis, Director, Division of Resident and Reactor FROM:
Project Inspection
SUBJECT:
SOUTH CAROLINA ELECTRIC ANJ GAS COMPANY, V. C. SUftflER UNIT 1, DOCKET 50-395, STATUS OF FACILITY COMPLETION the In accordance with inspection Procedure No. 94300B, the enclosures list remaining open items that require resolution _befora findings of readiness for endnrced by NRF. Roninn-!! 7 Remaining construction testing, and A 6peration may no inspection items identified in the enclosures have been categorized by our recommended mandatory completion milestones.
The licensee's projected fuel loading date is late March 1982.
Region II k
considers fuel loading date of mid April to be achievable, a
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- R 6q. C. Lewis
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Enclosures:
d>Jp A 1.
Items to be completed prior to V
Fuel Loading ',
2.
Items to be completed prior to Initial CriticaTiti' 3.
Items to be completed prior to Exceeding 5". Rated Power 4.
Items to be completed prior to Full Power Operation 5.
Preoperational Testing Status and Operational Preparedness 6.
Construction Status 7.
Status of Inspections Required by i1C 2512, MC 2513, and MC 2514 cc:
J. Taylor, DDRP B. Grimes, DDEP E. Jordan, DDEQA L. Cobb, DDFFliS B. Kane, LPM
Contact:
V. L. Brownlee 242-5577 8203220155 820316 PDR ADOCK 05000395 G
/
ENCLOSURE 1 N
ITEftS TO BE COMPLETED PRIOR TO FUEL LOADING f
/
/
I.
The licensee will complete the commitment to review, rewrite and approve all General Operating Procedures, Systems Operating Procedures and Emergency Operating Procedures and resolve any further commments after an NRC Region 11 (82-06-03), (82-06-04) (81-31-01) (81-31-02) (81 )
(
- 05) procedure reviev.(81-28-06) (81 28-07) (81-23-03) (81-23-07) (81-23-08) (8 j
(80-29-04) (80-25-03.)_(80-25-04)..(80-25-05)l80-15-03F II. The licensee will complete to the satisfaction of NRC Region II the require-ments of the following bulletins:
A.
Audibility problems encountered during evacuation alarm in high noise area (79-BU-18)
B.
Possible loss of ENS with loss of cffsite power (80-BU-15)
III. The licensee will complete to the satisfaction of NRC Region II the following Construction Deficiency Peports (50.55e items) and Part 21 identified items:
A.
Correct ASCO solenoid valve failures in the safety-related air system (79-30-04)
B.
Inadvertent boron dilution while using the residual heat removal system (80-37-05)
C.
Correct the use of unqualified Kerite splice material used on safety-related control and power cables.
(81-32-03)
IV. The licensee will complete to the satisfaction of NRC Region 11 the following open items:
A.
Administrative Procedure (AP-101) conflicts with Standard Technical Specification.
(79-28-02)
B.
Establish details to leak check accumulator check valves (79-31-01)
C.
Low battery voltage alann does not exist in control room as committed to in FSAR section 8.3.2.15.2 (79-37-03)
D.
Complete for review the test deficiency list evaluation and categori-zation of test deficiencies that will exist at core load date (80 02)
E.
Resolve preoperational safety injection test SI-3, accummulator blowdown test results (80-13-06)
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F.
Perform a comparison of RCS thermal growth with predicted values to confinn no undue stress (80-22-03)
G.
Install orifice to limit the boron dilution rate to less than 150 gpm.
(81-31-05)
H.
Correct H. P. training program problems (80-33-02)
I.
Complete area radiation monitor installation and testing (80-33-07)
J.
Verify preservice inspection has been satisfactorily completed and that no rejectable indications remain uncorrected (81-17-02)
K.
Resolve reporting inconsistencies in preservice inspection records (81-17-03)
L.
Perform correct installation of the liquid filter vent and the piping (81-21-01)
M.
Fire proof ladder opening on IE switchgear (81-29-06)
N.
Resolve NRC comments of surveillance test procedure review (STP 103.002, STP 104.002, STP 104.003, STP 104.004, STP 104.005, STP 120.001, STP 120.003, STP 128.002 and STP 144.001) (81-29-07, 08, 09,10,11,12) 0.
Establish administrative controls to remove power from the RHR suction isolation valves.
(81-31-07)
P.
Resolve NRC review comments of preoperational leak detection test LD-2.
(81-32-02)
Q.
Resolve NRC comments on the Plant Safety Review and the Huclear Safety Review Committees.
(81-32-04)
R.
Resolve concerns regarding preservice inspection of the pressurizer support weld (82-02-01)
S.
Establish and have available to the operators the as-built flow diagrams (82-06-02)
T.
Complete the installation of permanent plant fire protection equipment and systems (82-09-02)
U.
Perform an evaluation on the adequacy of the emergency breathing air supply to the fire brigrade and resolve problems (82-09-02)
V.
Complete the revision to the fire protection administrative control procedures (82-09-03)
3 W.
Resolve descrepancies between the fire protection features provided and those listed in the SER (82-09-04)
X.
Evaluate the adequacy of welds and bolting for the reactor vessel head lifting structure.
(82-13-02)
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's ENCLOSURE 2 ITEMS TO BE COMPLETED PRIOR TO INITIAL CRITICALITY I.
The licensee will complete to the satisfaction of NRC Region II the
~ requirements of the following bulletins:
A.
Pipe support base plate designs using concrete expansion anchor bolts (79-BU-02)
B.
Seismic analysis for as-built Safety-Related piping systems (79-BU-14)
C.
Surveillance of mechanical snubbers (81-BU-01)
. L. kJ II. The licensee will complete to the satisfaction of NRC Region 11 the following Construction Deficiency Reports (50.55e items) and Part 21 identified items:
\\
A.
Establish. corrective measures to correct deficiencies regarding rod drop analysis (80-05-02)
B.
Correction of overspeed tripping upon restart of the Terry Turbine within 30 minutes after shutdown (80-16-06)
C.
Corroded hermetic connectors in containment electrical penetrations (81-05-10)
D.
Turbine driven emergency feedwater pump lube oil cooler not correct for pump (81-08-09)
E.
Diesel generator fuel oil line missing pipe supports -(81-28-01)
F.
Correct diesel generator slow start times attributed to fuel oil header drain down (81-29-01)
G.
Service water pump oil leakage around upper bearing pot (81-29-03)
H.
Resolve the problem concerning Westinghouse containment isolation valves. (82-06-01) i I
2 III. The licensee will complete to the satisfaction of NRC Region II the following open items:
A.
Re: inspect areas shimed after HFT (80-22-01)
Md B.
Reinspect supports and restraints which were adjusted after HFT (80-22-02) Aw s
C.
Complete commitments made in question 211.25 of FSAR concerning RHR suction valves (80-25-06)
D.
Resolve Emergency Feedwater Reliability Analysis report which describes system features that do not exist (80-29-02)
E.
Modify particulate monitors to maintain a 1.0 cfm airborne sampling rate (80-31-01)
F.
Revise and update environmental surveillance procedures manual to identify equipment calibration and maintenance (80-32-02)
G.
Rearrange entrar.ce to radiation control area access (80-33-03)
H.
Complete area radiation monitor installation and testing (80-33-07)
I.
Complete the Emergency Feedwater system commitments (81-03-04)
J.
Clarify preservice valve program basis (81-05-18)
K.
Correct equivalent piping resistance values (L/D values) in preopera-tional safety injection test SI-3 results.
(81-08-04)
Correct preoperational reactor building spray test SP-3 results.
(81-08-05)
H.
Resolve preoperational reactor building spray test SP-2 acceptability (81-08-07)
N.
Resolve the problem of the discharge isolation valves being to close to the sample monitoring point to prevent a release (81-11-01) 0.
Verify that bolt skewness on concrete expansion anchors does not reduce the safety factor below acceptable criteria (81-16-01)
P.
Review method of locking 36" purge valves shut (81-29-05)
Q.
Verify that temporary cable is capable of use during emergency if RHR pump cooling units need repair.
(81-31-03)
R.
Resolve NRC comments on cooldown made from Control Room Evacuation panel (81-31-04)
3 S.
Complete modifications to separate the auctioneered temperature circuits for the control and interlock functions (81-31-06)
T.
Install special clamp to eliminate flexing of the acoustic transducer connection on the pressurizer safety valves (81-32-05)
U.
Resolve NRC concerns regarding the adequacy of installation of locking devices (82-13-01).
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ENCLOSURE 3 ITEMS TO BE COMPLETED PRIOR TO EXCEEDING 5% RATED POWER I.
The licensee will complete to the satisfaction of NRC Region 11 the requirements of the following bulletins:
A.
Maintenance of adequate minimum flow through centrifugal charging pumps following secondary side high energy line rupture (80-BU-18)
B.
Failure of gate type valves to close against differential pressure (81-BU-02)
II.
The licensee will complete to the satisfaction of NRC Region II the following Construction Deficiency Reports (50.55e items) and Part 21 identified items:
A.
Charging / Safety injection pump damage due to secondary line break and no flow (80-29-01)
B.
Westinghouse 3 inch gate valve closure failure (80-37-10)
C.
Sodium hydroxide tank relief valve not suitable for application (81-05-08)
D.
Westinghouse 4 inch gate valves closure failure (81-05-09)
E.
Improper termination of solenoid valve which could result in failure of the reactor building air compressor suction valve (81-23-01)
III. The licensee will complete to the satisfaction of NRC Region II the following open items:
A.
Correct the hydrogen recombiner HI hydrogen alarm set at 6% versus proposed Technical Specification limit of 2% (80-06-07)
B.
Install and test the post-accident containment atmosphere sampling system and conduct training on the system's use for appro-priate personnel (81-12-11)
C.
Install and test of the post-accident gaseous and particulate effluent sampling system and conduct training on the system's use for appropriate personnel (81-12-12)
D.
Install and test the high range Reactor Building Area Monitor (81-12-23)
2 i
i E.
Demonstrate the capability to account for all personnel onsite within about 30 minutes (81-12-51).
F.
Approval and implemer.tation of the Corporate Emergency Management Plan (81-12-54)
G.
Correction of deficiencies identified in the Prompt Notification System for warning the public within the 10 mile Emergency Planning Zone (82-03-02).
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i ENCLOSURE 4 ITEMS TO BE COMPLETED PRIOR TO FULL POWER OPERATION 4
I.
The licensee will complete to the satisfaction of NRC Region II the following open items:
A.
Resolve the problem of the' reactor building temperature being greater than expected during hot functional testing (80-25-09)
B.
Installation of control room habitability items to sustain seven people for seven days after an accident (80-29-07)
C.
Incorporation of control room human factors audit review commitments (81-03-08)
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o ENCLOSURE 5 PRE 0PERATIONAL TESTING STATUS AND OPERATIONAL PREPAREDNESS Preoperational Test Status Preoperational Testing is approximately 85% complete. Hot Functional Testing is complete.
The overall status of the test program is summarized below.
- Tests
- Started
- Completed Approved Preops required 136 132 113 90 for Fuel Load Preops required 32 3
0 0
After Fuel Load 191 of the 234 functional tests requiring completion prior to fuel loading have been completed and approved.
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ENCLOSURE 6 CONSTRUCTION STATUS As of February 1982, construction was 99% complete.
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ENCLOSURE 7 STATUS OF INSPECTIONS REQUIRED BY MC 2512, MC 2513 AND MC 2514 All modules in the Regional inspection program are considered complete except as noted below:
Percent MC 2512 Complete 47065B Containment (Prestressing) - Review of 90 Quality Records 50090B Safety-Related Pipe Support and 90 Restraint Systems 73051B Inservice Inspection - Review of Program 90 7055B Preservice Inspection - Observation of 90 work and work activities Percent MC 2513 Complete 36301B Operational Staffing Inspection 80 37301 Comparison of As Built to FSAR 0
Description 40301B Safety Canmittee Activity Inspection 80 41301B Inspection of Operationing Staff Training 0
42450B Operating Procedures Inspection 90 42452B Emergency Procedures Inspection 80 70322B Evaluation Test Results ESF 0
70323B Evaluation Test Results CLIRT 0
tjftcc) 70324B Evaluation Test Results HFT 0
70325B Evaluation Test Results RPS 0
70326B Evaluation Test Results Loss of Offsite 0
Power
2 70329B Verification that Tests are Evaluated 0
by Licensee 71301B Technical Specification Review 90 81x10B theu Physical Protection 33 81x90B 82331B Emergency Plan - Facilities 50 equipnent, Procedures 833208 Radiation Protection - Preoperational 70 inspection 84330B Radioactive Waste Systems - Preoperational 50 Liquid and Solid Waste System 84331B Radioactive Waste Systems - Preoperational 40 Gaseous Waste System 84332B Radioactive Waste Systems - QC and 40 capasility Test 85102B ltaterials Accountability 90 Percent MC 2514 Complete 72500B Initial Fuel Loading Procedure Review 90 72564B Pre-critical Test Procedure Review 90 (Protective Trip Circuit or Rod Drop Measurements) 72566B (Pre-critical Test Procedure Review 0
(RCS Leak Test or Pressurizer Effectiveness) 72570B Low Power Test Procedure Review (Initial 90 Criticality) 72576B Power Ascension Phase Procedure Review 0
(Natural Circulation or Power Reactivity Coefficient Measurement) 725788 Power Ascension Phase Procedure Review 0
(Evaluation of Core Performance (A&B))
72580B Power Ascension Phase Procedure Review 0
(Turbine Trip or Generator Trip)
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3 1
72582B Power Ascension Phase Procedure Review 0
(Shutdown from Outside Control Room) j (Group A) 72583B Power Ascension Phase Procedure - LOP 0
725848 Power Ascension Procedure Review 0
I (Asymmetry or Psuedo Rod Ejection Test) l
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UNITED STATES OF # ERICA hTCIEAR REGUIATORY CQt11SSION BEFORE IlE AIUiIC SAFETY AND LICENSING BOARD In the Matter of
)
)
SOUIll CAROLINA EIECIRIC & GAS
)
CCMPNW
)
Docket No. 50-395
)
(Virgil C. Sunmer Nuclear Station,
)
Unit 1)
)
CERTIFICATE OF SERVICE I hereby certify that copies of "NRC STAFF RESP 0flSE TO IflTERVEfl0R'S 110 TION FOR ADl11SSI0ft 0F NEW C0flTEflTI0'1" dated March 16, 1982 in the above-captioned proceeding have been served on the following by deposit in the United States mail, first class, or as indicated by an asterisk through deposit in the fluclear Regulatory Commission's internal mail system this 16th day of March, 1982:
- Herbert Grossman, Esq., Chainnan Richard P. Wilson, Esq.
Administrative Judge Assistant Attorney General Atanic Safety and Licensing Board S. C. Attorney General's Office U.S. Nuclear Regulatory Camlission P. O. Box 11549 Washington, DC 20555 Columbia, South Carolina 29211 Dr. Frank F. Hooper Joseph B. Knotts, Jr.
Administrative Judge Debevoise & Liberman School of Natural Resources 1200 Seventeenth Street, N.W.
University of Michigan Washington, DC 20036 Ann Arbor, Michigan 48109 Randolph R. Mahan, Esq.
- Mr. Gustave A. Linenberger S. C. Electric & Gas Company Administrative Judge P. O. Box 764 Atomic Safety and Licensing Board Columbia, SC 29218 U.S. Nuclear Regulatory Camnssion Washington, DC 20555
- Atomic Safety and Licensing Board Panel George Fischer, Esq.
U.S. Nuclear Regulatory Camtission Vice President and General Counsel Washington, DC 20555 South Carolina Electric and Gas Caupany i
P. O. Box 764
- Atomic Safety and Licensing Appeal j
Columbia, South Carolina 29202 Board Panel i
U.S. Nuclear Regulatory Conmission Brett Allen Bursey Washington, DC 20555 Route 1, Box 93-C Little Mountain, South Carolina 29076 i
- Docketing and Service Section Office of the Secretary U.S. Nuclear Regulatory Ccmnission Washington,DC 20555 A.
w Steven C. Goldberg &
Counsel for NRC Staff I
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