ML18136A251
| ML18136A251 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/24/1979 |
| From: | Burke D, Kellogg P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18136A248 | List: |
| References | |
| 50-280-79-55, 50-281-79-73, NUDOCS 7912050467 | |
| Download: ML18136A251 (5) | |
See also: IR 05000280/1979055
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100
ATLANTA, GEORGIA 30303
Report Nos. 50-280/79-55 and 50-281/79-73
Licensee: Virginia Electric and Power Company
Richmond, Virginia 23261
Facility Name: Surry Units 1 and 2
Docket Nos. 50-280 and 50--281
License Nos. DPR-32 and DPR-37
Inspection at
SUMMARY
Inspection on August 20 through September 7, 1979.
Areas Inspected
Si
Da~~
This routine inspection by the resident inspector involved 80 inspector-hours
onsite in the areas of plant operations and maintenance, including the Unit 2
steam generator replacement outage work, and followup on IE Bulletins and pre-
viously identified items.
Results
Of the four areas inspected, no apparent items of noncompliance or deviations
were identified in three areas; one apparent item of noncompliance was found in
one area (Infraction - failure to follow radiation control procedures (280/79-
55-01) paragraph 6).
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1.
Persons Contacted
Licensee Employees
DETAILS
Virginia Electric and Power Company (VEPCO)
- W. L. Stewart, Station Manager
- J. L. Wilson, Superintendent, Operations
- T. A. Peebles, Superintendent, Technical Services
- R. F. Saunders, Superintnendent, Maintenance
R. M. Smith, Supervisor, Health Physics
G. Kane, Operating Supervisor
- F. L. Rentz, Resident QC Engineer
D. A. Christian, Engineering Supervisor
Other licensee employees contacted during this inspection included control
room operators, shift supervisors, QC, engineering, HP,
plant maintenance, security, engineering, and administrative personnel.
- Attended management interviews.
2.
Management Interviews
The scope and findings were summarized on a weekly basis with those persons
indicated in Paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings
Not inspected.
4.
Unresolved Items
Unresolved items were not identified during this inspection.
5.
Unit 2 Steam Generator Replacement Activities
The inspector reviewed certain U-2 SG replacement and associated activities
to verify that the activities were performed in accordance with the Steam
Generator Repair Program (SGRP) and applicable procedures.
The review included the following activities:
a.
Inspection tours of the Unit 2 containment for cleanliness and radia-
tion control; appropriate work and radiation controls were being
implemented.
b.
Review of certain contractor and plant personnel radiation exposure
records to verify that radiation work was appropriately controlled.
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The licensee notified the inspector of an apparent overexposure when a
contracted employee's TLD was read, but discussion with the employee
and review of the individuals dosimetry readings and _work history
could not substantiate the TLD findings; NRC and licensee followup is
continuing.
c.
Replacement of the degraded Unit 2 reserve station service cable
identified during the high potential testing (ST-63) (See IE Report
50-280/79-46 and 50-281/79-65).
Within the areas inspected, no items of noncompliance were identified.
6.
Unit 1 Operations and Maintenance
The NRC Order to Show Cause dated March 13, 1979, which resulted in Unit 1
shutdown, was lifted on August 22, 1979.
However, Unit 1 remains shutdown
pending resolution of I and E questions concerning IE Bulletins 79-02
(Anchor bolts & baseplates), and 79-14 (As-built piping systems verifica-
tion).
The inspector toured the control room and certain Unit 1 plant
areas to verify that the shutdown operations were in accordance with the
Technical Specifications and facility procedures.
Within the are*as in-
spected, one item of noncompliance was identified (infraction 280/79-55-01)
when the inspector observed two welders grinding and welding on a feedwater
line in Unit 1 containment without the respiratory protection required by
special RWP 621-A.
Subsequent licensee sampling and whole body counts of
the*individuals involved determined that no contamination or body uptake
resulted from the work.
Specific areas of inspection included:
a.
Followup on the boric acid filter material deterioration (open item
280/79-31-01); the Cuno filter charts indicate that the wound nylon
filter material may not be compatible with the heated boric acid
environment.
The licensee stated that the filters -would be changed to
a more suitable material, such as polypropylene, when their evalua-
tions are complete and the filters are in-stock.
This item is closed.
b.
Observation of the steam generator feedwater line repairs which re-
sulted from the inspection and .examination work performed per IE
Bulletin 79-13 (see noncompliance identified above).
c.
Walkdown of certain piping systems such as safety injection and con-
tainment recirculation spray (from lC µeat exchanger) to verify that
pipe support modifications had been performed in accordance with the
sketches and MKS drawings for the modifications resulting from as-
built verification or analyses.
One apparent discrepancy was iden-
tified; the shims on one containment spray pipe vertical support did
not appear to be installed in accordance with th~ modification sketch.
The licensee reviewed the discrepancy and corrected the shim instal-
lation.
d.
The inspector remained on-site during the aftermath of hurricane David
which passed through the area on the evening of September .5, 1979..
No si:te
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problems resulted when the remains of the storm passed through the
area.
In preparation for the storm, the licensee took precautions to
lower outside crane booms, test the emergency diesel-generators, and
verified that adequate supplies of diesel fuel were available on-site.
Additional personnel and communications links were also available.
e.
Review of plant logs and records for August, 1979, and verification
that the control rooms were staffed in accordance with Technical
Specification 6.1.
7.
IE Bulletin Followup
a.
b.
IE Bulletin 79-0lA, "Environmental Qualification of Class IE equipment
(ASCO Solenoid Valves)".
The inspector reviewed certification and .
purchase order documents for the ASCO solenoid operated pilot valves
(SOV) used inside Unit 1 containment and inspected the SOV's installed
in containment. Recently, the licensee replaced SOV's #8320Al02 on
the three SG blowdown isolation line valves inside containment after
the SOV's were determined to be environmentally unqualified.
(See LER 280/79-18) Although the new SOV's which were installed appeared to
have the appropriate high temperature coils-and metal parts, the
licensee could not verify that the Buna-N type materials in the SOV
were replaced with EP or Viton materials.
Since environmentally qualified ASCO SOV's (NP series) were available,
the licensee installed these SOV's on the SG blowdown isolation valves.
Qualified ASCO SOV's were also installed on valves such as the inside
containment sump valve (TV-D-200A), letdown, and the pressurizer*
power-operated relief valves. Additional SOV's inside containment are
being evaluated by the licensee. This Bulletin remains open pending
review of the licensee's evaluations.
LER 280/79-18 is closed.
IE Bulletin 79-04, "Incorrect Weight for Velan Check Valves".
The
inspector reviewed documentation which verified that corrective action
was taken on the discrepancies identified in IE Reports 50-280/79-33
and 50-281/79-51, paragraph S.S.
Analysis of the data determined that
the installations were adequate to support the corrected valve weights.
This bulletin is closed.
8.
Plant Physical Protection
The inspector verified the follwing by obse~ation:
a.
~ - b.
Gates and doors in protected and vital area barriers were closed and
locked when not attended.
Isolation zones described in the physical security plans were not
compromised or obstructed.
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c.
Personnel were properly identified, searched, authorized, baqged and
escorted as necessary for plant access control .
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