ML20010H542
| ML20010H542 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/09/1981 |
| From: | Baer R, Knapp P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20010H540 | List: |
| References | |
| 50-334-81-23, IEB-80-10, NUDOCS 8109240603 | |
| Download: ML20010H542 (4) | |
See also: IR 05000334/1981023
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE-Or' INSPECTION AND ENFORCEMENT
Region I
l
Report No.
- D-334/81-23
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Docket No.
50-334
License No.
Priority
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Category
C
Licensee:
Duquesne Light Company
Pos* uf' ice Box 4
Snippingport, Pennsylvania 15077
Facility Name:
Beaver Valley Power Station, Unit 1
Inspection at:
Shippingport. Pennsylvania
Inspection conducted: July 8 and 9, 1981
f/ 8
Inspectors:
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A'.' t .
c.diation Specialist
dat'e signed
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Approved by: 'M h~
O
1-7 - D
P. J. Knapp, Chief, Facilith'Raciologir--I
~date signed
Protection Section, Technical Inspection
Branch
Inspection Summary:
Inspectior on July 8 and 9,1981 (Report No. 50-334/81-23)
Areas Inspected:
Inspection of the licensee's response to IE Bulletin 80-10
conducted in conjunction with special, unanncunced inspection 81-19. Areas
inspected included the review of the facility design and operation; sampling /
analysis monitoring program; CJrrent status of Contaminated nonradioactive
systems. The inspection involved 5 inspector-hours onsite by one regional
based inspector.
Results: Of the three areas inspected, no items of noncompliance were identified.
Region I Form 12
(Rev. April 77)
%092406038109go
ADOCK 05000334
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DETAILS
1.
Persons Contacted
- Mr. J. C. Allingham, Health Physicist, DLC
- Mr. G. L. Beatty, Quality Assurance Engineer
- Mr. R. F. Burski, Sr. Licensing Engineer, DLC
.r. H. Jenkins, Operations Foreman
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- Mr. J. A. Kosmal, Radcon Supervisor
Mr. W. S. Lacey, Chief Engineer
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Mr. V. J. Linnenbom, Radiochemist
- Mr. S. Sovick, Compliance Engineer, DLC
- Mr. J. W. Wenkhous, Reactor Control Chenist
Mr. H. P. Williams, Superintendent
Other Personnel
- Mr. D. A. Beckman, Senior Resident Reactor Inspector, USNRC
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The inspector also interviewed several other licensee and contractor
employees including health physics technicians and operations personnel.
- denotes those persons present at the exit interview on July 9, 1981.
2.
Review of Facility Design and Operation
The inspector reviewed the licensee's resp 3nse to IE Bulletin 80-10. Tile
response, dated July 7,1980 transmits .the licensee's review, dated May
29, 1980. This review identified systems.that are considered nonradioactive,
but could possibly become radioactive. He informed the licensee's represen-
tative that two additional plant systems, the equipment and floor drainage
system and the facility yard storm drainage system, identified.since
Bulletin 80-10 was issued, should receive special consideration'by the
licensee. The licensee had not included these systems in their initial
review; subsequent to IE Bulletin 80-10, hen-implemented a sampling
the licensee received information
addressing these systems. The licensee t
program of the yard storm drainage system and reviewed the equipment and-
floor. drainage system. The systems initially reviewed are as follows:
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Reactor Plant River Water System
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Primary Grade Water System / Liquid Waste System
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Auxiliary Steam / Condensate /Feedwater/ Main Steam / Blowdown Systems
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Demineralized Water System
Filtered Water System / Chilled Water System
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Sewage Treatment System
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Instrument / Service Air Systems
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Hydrogen / Nitrogen Gas Systems
The licensee also reviewed existing procedures that had potential for
cross-contaminating nonradioactive liquid systems with radioactive systems.
The licensee's Onsite Safety Committee (OSC) reviewed and approved all
recommendations made in the licensee's review which included cutting and
capping water lines, installing locking devices on valves and sealing off
specific floor and sink. drains.
Operating Manual Change Notices were
approved and issued which addressed valve positions to reduce the potential
of cross-contamination between radioactive and nonradioactive systems.
The inspector had no further questions on this topic.
3.
Sampling / Analysis or Monitoring Program
The inspector reviewed the implementation of the routine sampling schedule
the licensee had initiated in responce to IE Bulletin 80-10 requirements.
The OSC had recommended a surveillance frequency of' quarterly.
Charistry
procedures were charged to incorporate this requirement.
Samples are
taken on some systems at a more freqctnt interval.
The licensee stated that the-lower limit of detectability for liquid
systems are less than 4E-6, microcuries per milliliter for tritium, and
7E-7 microcuries per milliliter for gross beta gamma activity.
It has
not been found necessary to sample the Hydroger/ Nitrogen Gas System to
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date. Sampling'is required only when the pressure within the gas bottle
drops below 100 psig. A posting at the nitrogen bottle station requires
that the Radiation Control Section be notified immediately if pressure
drops below 100 psig. The Instrument / Service Air System is operated at
a higher pressure than the containment side air system.
The licensee
will analyze samples frem this system prior to using it for a source of
breathing air.
The inspector had no further questions on this topic.
4.
Current Status of Contaminated Nonradioactive Samples
The inspector reviewed the current status of the plant systems. All
samples from plant nonradioactive systems indicated no activity above the
lower limits of detectability listed above.
The inspector had no further questions on this topic.
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5.
Exit Interview
The inspector met with-the licensee representatives-(denoted in Paragraph'
1) at the conclusion of the inspection on July 19, 1981. The inspector
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summarized the scope of the. inspection and the findings.
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