ML18114A721
| ML18114A721 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/30/1979 |
| From: | Murphy C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Proffitt W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| Shared Package | |
| ML18114A722 | List: |
| References | |
| NUDOCS 7906250137 | |
| Download: ML18114A721 (7) | |
See also: IR 05000281/1979014
Text
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET,N.W.
ATLANTA, GEORGIA 30303
MAR 3 0 1979
In Reply Refer To:
l
RII :JDW
S0-1281/79-14
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Virginia Electric and Power Company
Attn:
Mr. W. L. Proffitt
Senior Vice President, Power Operations
Post Office Box 26666
Richmond, Virginia
23261
Gentlemen:
This refers to the inspection conducted by Mr. J. D. Wilcox, Jr. of this
office on March 6-9, 1979 of activities authorized by NRC Operating
License No. DPR-37 for the Surry Power Station facility, Unit No. 2, and
to the discussion of our findings held with Mr. W. L. Stewart at the
conclusion of the inspection.
Areas examined during the inspection and our findings are discussed in
the enclosed inspection report.
Within these areas, the inspection
consisted of selective examinations of procedures and representative
records, interviews with personnel, and observations by the inspector.
We have examined actions you have taken with regard to previously reported
unresolved items.
The status of these items is discussed in the enclosed
report.
During the inspection, it was found that certain activities under your
license appear to be in noncompliance with NRC requirements.
This item
and references to pertinent requirements are listed in the Notice of
Violation enclosed herewith as Appendix A.
This notice is sent to you
pursuant to the provisions of Section 2.201 of the NRC's "Rules of
Practice", Part 2, Title 10, Code of Federal Regulations.
Section 2.201
requires you to submit to this office, within *20-days of your receipt of
this notice, a written statement or explanation in reply including:
(1)
corrective steps which have been taken by you, and the results achieved;
(2) corrective steps which will be taken to avoid further noncompliance;
and (3) the date when full compliance will be achieved.
In accordance with Section 2.790 of the NRC's "Rules of Practice,"
Part 2, Title 10, Code of Federal Regulations, a copy of this letter and
the enclosed inspection report will be placed in the NRC's Public Documf'nt
Room.
If this report contains any information that you (or your contractor)
believe to be proprietary, it is necessary that you make a written
application within 20 days to this office.to withhold such information
from public disclosure.
Any such application must include a full statemenl::S:p
of the reasons on the basis of which it is claimed that the information
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Virginia Electric and
Power Company
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MAR 3 0 1979
is proprietary, and should be prepared so that proprietary information
identified in the application is contained in a separate part 1of the
I document.
If we do not hear from you in this regard within ~tt= specified
1 period, the report will be placed in the Public Docwnent Rooin.J
.
Should you have any questions concerning this letter, we will be glad to
discuss them with you.
Enclosures:
Sincerely,
cc/:/;;,.J-,1
Charles E. ~~y, Cp{ef
Reactor Construction and
Engineering Support Section
1.
Appendix A, Notice of Violation
2.
Inspection Report No. 50-281/79-14
cc w/enclosures:
Mr. W. 1: Stewart
Station Manager
Surry Power Station
Post Office Box 315
Surry, Virginia 23883
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APPENDIX A
Virginia Electric and Power Co.
C
f Surry Nuclear Plant, Unit 2
Based on the NRC inspection March 6-9, 1979, certain of your activities
were apparently not conducted in full compliance with NRC requirements as
indicated below.
These items have been categorized as described* in corre-
spondence to you dated December 31, 1974.
As required by 10 CFR, Part 50, Appendix B, Criterion XVII, as imple-
mented by VEPCO's licensing submittal (Steam Generator Project, Surry
Power Station Units Nos. 1 and 2 - Revision 9). "Sufficient records
shall be maintained to furnish evidence of activities affecting quality
Inspection and test records shall, as a minimum, identify the
inspector or data recorder, the type of observation, the results; the
acceptability, and the action taken in connection with any dificiencies
noted.
Records sha11 be identifiable and retrievable".
Process Specifications NPT-91 and 94 require that the monitoring
schedules for nitrogen pressure gage readings of primary and secondary
sides to the steam generator lower assemblies shall be documented.
Contrary to the above, on March 8, 1979, the S. G. Lower assemblies
identified as f/2927, #2973 and #2981 had no official records for
nitrogen pressure gage readings.
This is a deficiency.
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, N.W.
ATLANTA, GEORGIA 30303
f Report No. 50-281/79-14
I
Licensee: Virginia Electric and Power Company
P. 0. Box 26666
Richmond, Virginia 23261
Facility Name:
Surry Power Station, Unit 2
Docket No. 50-281
License No. DPR-37 *
Inspection at Surry Site near Williamsburg, Virginia
'JD * **') C7
Inspector~ d'-;__,.. ~' ~
J. D. Wi cox, Jr.
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App roved by :
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A.
RC&ES Branch
SUMMARY
Inspection on March 6-9i 1979
Areas Inspected
Dat7e Si'gned
This routine, unannounced inspection involved 28 inspector-hours onsite in
the areas of construction status pertaining to the steam generator replacement
(SGRP) for Surry Power Station storage of new steam generator lower units,
follow-up on previous identified unresolved item, QA Audit Revie .... * ,. and
observation of safety-related work activities.
Results
Of the five areas inspected, no apparent items of noncompliance or deviations
were identified in four areas.
One apparent i tern of noncompliance ...-as
.found in one area (deficiency - Inadequate records - Nitrogen Purge S. G. Lo~er
Assembly - paragraph 6) .
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DETAILS
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Persons Contacted
Licensee Employees
A.
- J.
- '
- J.
'i':T.
- R.
L. Parrish, III, Project Manager SGRP
W. Patrick, VEPCO
L. Wilson, Station Operations Superintendent
A. Peebles, Technical Services Superintendent
M. Smith, H. P. Supervisor
- R.
- E.
L. Baldwin, VEPCO, Supervisor, Administrative Services
P. DeWandel, Administrative Assistant
- F. L. Rentz, Resident QC Engineer
- P. P. Nottingham, H. P. Coordinator, SGRP
- C. W. Rhodes, Resident Engineer Construction SGRP
.,':y.
- R.
P. Mangum, Jr., Resident Engineer Project Control SGRP
E. Titone, Engineering Technician
,',M. D. Tower, VEPCO (Corporate QA)
~*:s. Sarver, VEPCO (Corporate HP)
Other licensee employees contacted during this inspection included 4
construction craftsmen, 4 technicians, l security force member, and 3
office personnel.
NRC Resident Inspector
- D. J. Burke
'l':Attended exit interview.
2.
Exit Interview
The inspection scope and findings were summarized on
with those persons indicated in Paragraph 1 above.
sununarized the scope of the inspection as follows:
status, QA Audit Review, Review of Previous Identified
ind Observation of safety-related work activities.
3.
Licensee Action on Previous Inspection Findings
March 9, 1979
The inspector
Construction
Unresolved Item
(Closed) Unresolved Item (280-281/79-04-0l) "ASME Code Requirements"
Per concurring telcon conversation from D. Neighbors (NRR) to J. D. ~ilcox.
Jr.
(IE:RII), the intent of Paragraph 2.3 of the Safety Evaluation
Report (SER) under "ASHE Code and Regulatory Guide Implementation is
- the following: All piping weld end preps, welding, and nondestructive
examination will be in accordance with the 1974 Edition of the ASME
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Code, including addenda through Winter 1976.
Therefore, the S.E.R.
agrees with VEPCO's submittal (Steam Generator Project,1Surry Power
Station Units Nos. 1 and 2, Revision 9) to NRR dated Au!:st 1977 for
the Surry Steam Generator Replacement (SGRP) pertaining to the ASME
Code Requirements. This item is closed.
Unresolved Items
Unresolved items were not identified during this inspection.
5.
Independent Inspection Effort
a.
Construction Status
b.
The biological shield walls are being removed from around the
steam generators of the Unit 2 Reactor Building. Installation of
Crane Wall jib cranes and monorail transport system are being
accomplished.
Containment floor and crane wall modifications are
also in progress.
The new steam generator lower assemblies are
being stored near the unloading dock on the James River in VEPCO's
construction security area.
Quality Assurance Audit
The inspector examined the following QA audit conducted by the
site VEPCO's QA unit for completeness, deficiencies found, correc-
tive action taken, timeliness and implementation taken.
Audit Number
Subject
SGRP 78-1
Tesi and Measuring Equipment
The audit reviewed was found to be conducted and documented in a
thorough, timely and objective manner.
No items of noncompliance or deviations were identified in the
above area. inspected.
c.
Observation of Safety-Related Work Activities
The following safety-related work was observed by the inspector
during the course of the inspection:
(1)
Preparation for installation of Crane wall jib cranes
(2)
Preparation for modification of Crane wall
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6.
(3)
(4)
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Preparation for removal of instrumentation, feedwater and
mainsteam piping from Steam Generators "A", "B'f and "C".
Preparation for cutting reactor coolant pipiJg for Steam
Generator "C"
No items of noncompliance or deviations were ident:i.fied in the
above areas inspected.
Storage of Steam Generator Lower Assemblies
The inspector observed the storage of four (4) steam generator lower
assemblies.
The lower assemblies are located near a unloading dock on
the James River in VEPCO' s construction security area.
The lower
assemblies were checked to ensure proper nitrogen purges were being
maintained as required by Westinghouse Process Specification NPT 91,
"Protective measures for long term storage of steam generator lower
assemblies" and NPT 94, "Protective measures for short term storage of
steam generator lower assemblies".
Paragraph 4. 0 of these process
specifications contain the following requirements:
The following
monitoring schedules for nitrogen pressure gage readings of primary
and secondary sides of the steam generator lower assemblies shall be
documented. The monitoring of the site storage will be to take pressure
gage readings daily for the first three days at the plant site. Also
take readings daily for the first three days after any handling of the
generator at the plant site. Thereafter, take pressure gage readings
every two weeks until the nitrogen charge is intentionally released
for installation into the nuclear steam supply system.
On March 8,
1979, the inspector observed that inadequate records were being main-
tained for monitoring pressure gage reading of primary and secondary
sides of three (3) lower assemblies (identified as #2972, #2973, and
- 2981). It should be noted that the primary side of lower assembly
identified as #t971 is presently having nozzles re endprepped; therefore,
a.purge is not being maintained on the primary side of this generator
assembly.
This is in noncompliance with 10 CFR 50, Appendix B*, Cri-
terion XVII as implemented by the VEPCO's licensing submittal (Steam
Generator Project, Surry Power Station Units Nos. 1 and 2 - Revision 9)
to the Steam Generator Project.
This is identified as deficiency
- 281/79-14-01 "Inadequate Records - Nitrogen Purge S. G. Lower Assembly".
No other items of noncompliance or deviations were identified.