ML19308A721
| ML19308A721 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/18/1979 |
| From: | Crocker H, Haverkamp D, Neely D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19308A720 | List: |
| References | |
| 50-289-79-18, 50-320-79-22, NUDOCS 7912040179 | |
| Download: ML19308A721 (38) | |
See also: IR 05000289/1979018
Text
U.S. NUCLEAR REGULATORY COMMISSION
0FFICE OF INSPECTION AND ENFORCEMENT
i
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td
Region I
50-289/79-18
Report No.50-320/79-22
50-289
Docket No. 50-320
License No. DPR-73
Priority
Category
C
---
Licensee: Metropolitan Edison Company
P.O. Box 542
Reading, Pennsylvnia 19640
Facility Name: Three Mile Island Nuclear Station, Unit 2
Inspection at: Middletown, Pennsylvania
Inspection conducted:
July 18 - August 14, 1979
Inspectors: Obb
3 ~
Sf pb9
D. R. Haverkamp, Lead Reactor Operations
date signed
Inspector
@W
bv
S)d M
D. R. Neely, Lead Radi& tion Specialist
date signed
>
date signed
Approved by:
CA-A -
9 / /f / d
'H. W. Crocker, Drief, IE Resident
66te sfigned
Office - TMI 2
Inspection Summary:
Inspection on July 18 - August 14, 1979 (Report Nos. 50-289/79-18 and
50-320/79-22)
Areas Inspected:
Special inspection by IE Resident Office Staff and
shift inspectors of:
licensee action on previous inspection findings; Unit 2
new and revised procedures; Unit 2 plant operations including records, per-
formance of tests, and general plant tours; in-plant health physics including
documentation, posting and labeling reviews, witnessing of (Unit 1 and 2)
activities, and area tours; and preoperational status of EPICOR II System. The
inspection included continuous shift coverage by both reactor operations
and radiation specialist inspectors.
Results:
Significant findings were brought to the attention of the
licensee management when identified.
7912040f
_
9
.
DETAILS
1.
Persons Contacted
Principal licensee and contractor personnel contacted during this
inspection are identified in the exit interview section of this
report.
2.
IE Inspection Participants
The following tabulation identifies the TMI-2 Resident Office
professional personnel participating in this inspection.
a.
Resident Office Staff
R. Conte, Reactor Operations Inspector, IE:RI, July 18 -
August 14, 1979
H. Crocker, Chief, IE Resident Office, IE:RI, July 30 -
'
August 14, 1979
P. Graham, Reactor Operations Inspector, IE:RI, August 6 -
August 14, 1979
D. Haverkamp, Lead Reactor Operations Inspector, IE:RI, July
18 - August 7,1979
J. Kinneman, Radiation Specialist, IE:RI, July 19, 31,
August 1-3, 1979
H. Kister, Chief, IE Resident Office, IE:RI, July 18 - July
31, 1979
R. Knoll, Reactor Operations Inspector Co-op, IE:RI, August
<
3 - August 14, 1979
D. Neely, Lead Radiation Specialist, IE:RI, July 18 - August
3, August 13-14, 1979
W. Raymond, Reactor Operations Inspector, IE:RI, July 18 -
August 14, 1979
J. Serabian, Radiation Specialist, IE:RI, July 18 - August 8,
August 14, 1979
'
C. Sweinhart, Reactor Operations inspector Co-op, IE:RI, July
18 - August 3,1979
J. White, Lead Radiation Specialist, IE:RI, August 6 - August
10, 1979
,
b.
Shift Reactor Operations Inspectors
J. Ashendon, IE:RII, August 7 - August 14, 1979
C. Brown, IE:RIII, July 18 - July 30, 1979
J. Carlson, IE:RV, July 18 - July 24, 1979
C. Chow, IE:RIII, July 31 - August 14, 1979
T. Daniels, IE:RIII, July 18 - July 30, 1979
R. Masse, IE:RIII, August 13 - August 14, 1979
J. Mcdonald, IE:RII, July 25 - August 8,1979
D. Price, IE:RII, August 8 - August 14, 1979
R. Smith, IE:RIV, August 7 - August 14, 1979
A. Wagner, IE:RII, July 18 - July 25, 1979
T. Young, IE:RV, July 24 - August 7,1979
'
.
2
c.
Shift Radiation Specialists
J. Everett, IE:RIV, July 18 - July 23,1979
J. Ewald. IE:RII. July 18 - July 27, 1979
R. Fish, IE:RV, August 7 - August 13, 1979
J. Hiatt, IE:RII, August 7 - August 14, 1979
'
L. Hueter, IE:RIII, July 26 - August 6, 1979
W. Millsap, IE:RII, August 6 - August 14, 1979
D. Miller, IE:RIII, July 18 - July 25, 1979
B. Murray, IE:RIV, July 24 - 30, August 2 - 6, 1979
T. Troup, IE:RII, July 18 - July 27, 1979
J. Wray, IE:RII, July 27 - August 6, 1979
L. Wilborn, IE:RIV, August 6 - August 14, 1979
R. Zavadoski, IE:RII, July 27 - August 7, 1979
3.
Licensee Action on Previous Inspection Findings
(0 pen) Inspecton Finding (320/79-13-01):
Qualification of Licensee
Contractor Health Physics (H.P.) Personnel.
The licensee has
submitted a draft Radiation Protection Plan that contains specific
requirements in the area of H.P. personnel qualifications.
Pending
review and final approval of the plan this item will remain open.
(0 pen) Inspection Finding (320/79-13-02):
Posting, Barricading and Access Control.
Inspector tours of
licensee controlled areas identified six High Radiation Areas
either not posted, barricaded or controlled (i.e. locked or manned).
(Details paragraph 6.b).
(0 pen)
Inspection Finding (320/79-13-03):
Dosimetry QA Irregularities.
In-depth inspector review identified areas remaining to be addressed
and corrected by the licensee.
(0 pen) Inspection Finoing (320/79-13-04):
Failure to perform job
specific airborne radioactivity evaluations. A technical meeting
was held on July 26, 1979, with resident staff in attendance, in
which the above inspection finding was discussed.
Based on the
above and other meetings, the licensee, in a letter dated August 6,
1979 has comitted to the review and revision of those procedures
defining the airborne radioactivity sampling program implemented to
meet the requirements of 10 CFR 20.201 (b).
Pending review of
procedural changes and field observation of implementation, this
item will remain open.
(0 pen) Inspection Finding (320/79-17-09):
Posting and Labeling of
Radioactive Waste. Additional inspector review identified a non-
posted Radioactive Materials storage area (Details, paragraph 6.a
(2)).
'
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3
(0 pen) Inspection Finding (320/79-17-20):
Curie Level Determination
of Radioactive packages for shipment.
Inspector review of revised
curie / rem conversion factors indicated possible underostimation of
total activity.
(Details, paragraph 6.a (1)).
4.
Facility Procedure Review
Operating Procedures (0P), Emergency Procedures (EP), and Special
Operating Procedures (SOP), including subsequent evisions, were
reviewed by the Resident Office during this inspection. The S0P's
are temporary procedures written for the TMI-2 Recovery Program
which govern special evolutions and/or use of off-normal plant
systems and these are de.mignated "Z" or "R" procedure depending on
date of generation.
Procedure review included both Health Physics and Operations aspects
with consideration of the following: (1) the procedure, when
implemented, would not degrade the containment of radioactive
material, jeopardize core cooling, or result in excessive personnel
exposure; (2) the procedure conforms to the general criteria of TS 6.8, " Procedures", TS 6.11, Radiation Protection Program, ANSI
18.7Property "ANSI code" (as page type) with input value "ANSI</br></br>18.7" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process., 1976; (3) the technical content of the procedure is adequate
to perform the intended evolution.
Procedures reviewed during this report period are listed below
together with dates (in parenthesis) on which IE comments were
completed.
2104-5.16, Chemical Cleaning Building Ventilation System, Revision
--
0, (July 18, 1979)
--
R-2-79-025, U-2 R. B. Atomsphere Gas Sampling Using HP-R-227,
Revision 1, (July 18, 1979)
- Design Criteria for WG-19-Temporary Sampling System, Revision 0,
--
(July 19, 1979)
Operating Procedure for CNSI Electro-Con Unit, (July 10,1979)
--
Radiological Controls Procedure for CNSI Electro-Con Unit
--
Operation,(July 20,1979)
--
CG-A.1 to CG-A.6, Capgun Alarm Responses, Revision 0, (August
3,1979)
--
OP 2104-4.9 EPICORE Prefilter and Demineralizer Changeout,
Revision 0, (July 27, 1979)
--
Transfer of WDL-T-2 (MWHT) to WDL-T-8A/B Primary
Neutralizer Tank, Revision 0, (July 18, 1979)
Containment Assessment Program - Procedure to Obtain Air
--
Sample and Preliminary Dose Map of Air Lock No. 2,
(July 25, 1979)
<
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4
2203-4.1 Loss of Demineralized Water for EPICOR-2 (July 20,
--
1979)
PCG-A.1 to .3 - Alarm Response (EPICOR II) Prefilter and
--
Demineralizers(August 3,1979)
Long Term B System Alarm Responses (July 20,1979)
--
Operation of SPC-P-3 in Recirculation Mode (July 20,1979)
--
--
OP 2203-1.9 Standby Pressure Control System on Rising RCS
Pressure (July 20,1979)
Fill Procedure for Steam Generator "B" with Water (July 20,
--
1979)
Long Term OTSG B Cooldown System Operating Procedure (July 20,
--
1979)
Condensat? Polisher Resin Removal (July 20,1979)
--
--
Containment Assessment Program - Procedure to Measure CB
Radiation Using Penetration R-626 (July 25,1979)
Filling BAMT with Boric Acid /and with Caustic Soda (July 30,
--
1979)
Z-51 Liquid Releases from Three Mile Island, Revision 4, (July
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26,1979)
- TMI-2 Permanent Sample System Draft Criteria (August 1,1979)
--
- EvaporatorProject(July 23,1979)
--
Radiological Controls for B&W Counting Area, Revision 0, (July
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25,1979)
Unit 2 Auxiliary and Fuel Handling Building Ventilation Flow &
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Mixing Measurement, Revision 0, (July 26, 1979)
EP 2202-4.4 Fire in Auxiliary Building Liquid Process System
--
(EPICOR II), Revision 0, (July 27,1979)
R-2-79-40 Radiation Controls B&W Chemical Trailer - CAPGUN B
--
Counting, Revision 1 (July 25, 1979)
Operating Procedure for CNSI ELECTR0-CON Unit, aevision 0,
--
(July 25,1979)
Radiation Controls for CNSI ELECTR0-GUN Operations, Revision 0
--
(July 25, 1979)
Processing Tank Truck Water Through " Cap-Gun"/ System (July 25,
--
1979)
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t
5
Depressurization of th JH System on the DH pump side of
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DH-V3, DH-V4, V-4B (July 30, 1979)
Moving Laundry and Respiratory Equipment to a Cleaning Facility
--
Outside the Plants Protective Area, Revision 0, (July 27,
1979)
1618.A Shipment of Radioactive Material and TCN to 1618,
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Radioactive Material Shipping (July 31,1979)
2104-4.12 EPICOR II Sampler Operations, Revision 0, (August 2,
--
1979)
2107-l.5 Balance of Plant (BOP) DG-B (White) Diesels and
'
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Auxiliaries, Revision 0, (August 1, 1979)
,
2107-1.6 Balance of Plant (B0P) DG-A (Gray) Diesels and
--
Auxiliaries, Revision 0, (August 1,1979)
OP 2104-4.11 Crud Filter Change-Out ALC-F-5, Revision 0, (July-
--
27,1979)
Transfer of Radioactive Resin Liners from EPICOR I to Onsite
>
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Staging Area, Revision 0, (July 31, 1979)
3104-4.4 Transfer U2 MWHT to Ul RCBT, Revision 0, (August 1,
--
1979)
--
Moving Laundry and Respiratory Equipment to Cleaning Facility
Outside Protected Area, Revision 0 (July 30, 1979)
R-2-79-35 Testing the SPC System, Revision 2, (July 31, 1979)
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Recovery Operation Reactor Building Remote Access (July 31,
--
1979)
Reactor Building Water Sampling (August 3, 1979)
--
Unit 2 Auxiliary and Fuel Building Ventilation Flow and Mixing
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Measurements (July 31,1979)
3104/4.4 Transfer from U-2 MWHT Te Unit 1 RCBT (August 1,
--
1979)
Moving Laundry and Respiratory Equipment to a Cleaning Facility
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Outside the Plant's Protective Area (July 31,1979)
Hydro Lansing of Unit I Sump (Auxiliary Building) (August 1,
--
1979)
- Evaluation Program - Post Decontamination Leaching Program
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(August 3,1979)
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-
.
2204-302B Radwaste - Gas and Solid, Revision 3, (August 3,
--
1979)
2104-4.50 Fuel Pool Waste Storage System, Revision 1, (August
--
2,1979)
2104-4.2 Waste Gas Disposal System (Including TCN), Revision
--
2,(August 3,1979)
Operation of Supplemental Fans and Filters (Auxiliary Building
--
Roof) (August 10,1979)
Loss of Service Air for EPICOR II (August 2,1979)
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Filling BAMT with Boric Acid and Caustic Solution,. Revision 0,
--
(August 3,1979)
Helium Leak Testing of Waste Gas System, Revision 0, (August
--
3,1979)
Respirator Facemask Cleaning and Testing Facility, Revision 0,
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(August 3,1979)
--
- Design Criteria Environmental Barrier Wall (August 13, 1979)
- Criteria Document and Scope Document for the Mini Decay Heat
--
,
Removal System (August 15,1979)
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--
EP (Draft) EPICOR I/II Transporter Vehicle Accident During
DemineralizerTransfer(August 14,1979)
Transfer Out of Spec Water from Unit II WDC-T-9A/B to EPICOR
--
CC-T-1 (August 14, 1979)
--
2104-4.7 Operation of Axiliary Building Emergency Liquid
Cleanup System, Revision 0 (August 14,1979)
CG-A.2,
.3, .5 GAPCUN Alarm Responses (August 10,1979)
--
PCG-A.1 to .3 Alarm Responses (EPICOR II) Prefilter and
--
Demineralizers (August 10,1979)
--
Discharge of WDG-T-1A(B) to Reactor Building, Revision 0,
(August 10,1979)
1618 B Receipt of Radioactive Materials, Revision 0, (August
--
14,1979)
2104-4.11 Change Out of Crud Filter (ALC-F5) Cartridge,
--
Revision 0 (August 14,1979)
3104-4.4 Transfer from Unit 2 MWHT to Unit 1 RC Bleed Trank,
--
Revision 0(August 10, 1979)
--
(August 14, 1979)
.
.
7
Z-39 Natural Circulation Operation, Revision 2 (August 14,
--
1979)
Transfer of WDL-T-10 (Unit I) to WDL-T-2 (Unit II), Revision 0
--
(August 14,1979)
1618-C Radioactive Material Handling, Revision 0 (August 15,
--
1979)
,
CNSI/VIREM DC-3 Support Procedure for Solidification of Radiac
--
Wash Waste Stored in U-2 Auxiliary Building, Revision 0
(August 15, 1979)
- Temporary Sampling System, Revision 0 (August 15, 1979)
!
--
- These are design criteria also submitted by the licensee and
.
'
reviewed for technical adequacy.
Composite NRC connents on procedures were forwarded to the licensee by
Office of Nuclear Reactor Regulation (NRR).
No instances of failure to
resolve NRC comments were identified.
5.
Review of Plant Operations
a.
Test Perfonnance/ Procedure Implementation.
The following tests / procedure implementations were witnessed.
R-2-79-42 Fuel Pool Waste Storage System, Revision 0
--
(July 18,1979), on July 29, 1979
--
R-2-79-52 Depressurization and Draining of Decay Heat
System on DH Pump Side of DH-V3, V4A, V4B, Revision 0
(July 27, 1979), on July 29, 1979 to August 14, 1979
l
OP 2104-4.13 Transfer of Radwaste Resin Liners, Revision
--
0, (July 31, 1979), on August 1, 1979
SOP No. R-2-79-56 Reactor Building Remote Access, Revision
--
0 (July 31,1979), on August 6, 1979 to August 14, 1979
R-2-79-15 Balance of Plant Diesel Generator (Grey) and
--
Auxiliaries Operating Procedure, Revision 0 (August 9,
1979), on August 9,1979
2303-M16D Emergency Diesel Generator and Cooling Water
--
Valve Operability Test (B Diesel), Revision 9 (March 26,
1979),onAugust9,1979
R-2-79-52 Drain of DH-V3 Header, Revision 0 (July 16,
--
1979), on August 12, 1979
.;
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- - - - .
- -
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8
R-2-79-14 Balance of Plant Diesel (White) and Auxiliaries
'
--
Operating Procedure, Revision 0 (August 15,1979), on
August 11, 1979
Z-2 Discharge of WDG-T-1B to Reactor Building, Revision 2
--
(April 6,1979), on August 12, 1979
R-2-79-44 SPC-P-3 in Recirculation Mode, Revision 0 (July
--
20,1979), on August 12-14, 1979
2107-1.6 Balance of Plant Diesel (Grey) and Auxiliaries
--
Operating Procedure, Revision 0 (August 15,1979), on
August 17, 1979
2303-M16C Emergency Diesel Generator and Cooling Water
--
Valve Operability Test (A Diesel), Revision 9 (March 26,
,
1979), on August 20, 1979
/
b.
Plant Tours
,
During the period July 18, 1979 through August 14, 1979, tours
of the following areas were conducted (number of tours are
indicated in parenthesis).
Cleanliness / Housekeeping conditions
were observed along with Radiological and Fire Protection
Measures.
In addition, for the specific areas listed, construction
status and testing progress were noted.
--
General Plant Area including outside and inside of the
protected area (4).
Fuel Handling Building accessible areas on elevation 305'
--
(11) and elevation 348' (11).
--
Chemical Cleaning Building including the Auxiliary
Building Emergency Liquid Cleanup System (EPICOR II)
(32).
Turbine Building, accessible areas on elevation 281'
--
(40), elevation 305 (49), and elevation 331' (47).
--
Diesel Generator Building accessible areas on elevation
305' (13) and elevation 280' (5).
Balance-of-Plant Diesel Generators Trailers & Fuel
--
Storage Area (5).
Control Building accessible areas on elevation 280' (40),
--
elevation 305' (32) and elevation 331', including the
Control Room (33).
Auxiliary Building control point on elevation 305' (26).
--
.
.
9
c.
Logs and Records
CR0 Log for period of July 24, 1979 through July 25, 1979, on
July 25, 1979.
Shift Foreman Log for period of July 24, 1979 through July 25,
1979, on July 25, 1979.
Locked Valve list on July 26, 1979.
CR0 Log for period of July 25, 1979 through July 26,1979, on
July 26, 1979.
Shift Foreman Log for period of July 25, 1979 through July 26,
1979, on July 26, 1979.
CR0 Log of July 26, 1979 on July 27, 1979.
Shift / Foreman Log of July 26, 1979, on July 27, 1979.
CR0 Log of July 28, 1979 on July 28, 1979.
Leak Rate Chart for period of July 26, 1979 through July 28,
1979, on July 28, 1979.
d.
Findings
The following Significant Inspection Findings were identified
during this review and details are appended to this report.
Inadequate Administrative Controls for Recovery Special
--
Operating Procedures (R-SOP) (Significant Inspection
Finding No. 79-22-01).
Adequacy of Fire Protection in Diesel Building (CLASS IE)
--
and Cable Spreading Room (Significant Inspection Finding
No. 79-22-02).
Adequacy of Operational Preparedness for Balance of Plant
--
(B0P) Diesels (Significant Inpsection Finding No. 79-22-03).
6.
In-Plant Health Physics
a.
Solid Radioactive Waste
The shipping, storage, handling and analysis of solid radio-
active waste was reviewed for compliance with the following:
10 CFR 20, " Standards for Protection Against Radiation".
--
10 CFR 71, " Packaging of Radioactive Material for Transport
--
and Transportation of Radioactive Material Under Certain
Conditions".
I
.
.
10
Station Health Physics Procedure 1620 Revision 4,
--
" Radiological Controls for Processing Radioactive Solid
Waste", dated February 9, 1979.
Special Operating Procedure, S0P No. R-2-79-6, Revision
--
1, "On-Site Solid Waste Storage for TMI-2", dated May 8,
1979.
Station Health Physics Procedure 1618, Revision 6,
--
" Shipment of Radioactive Material, D0T Regulations",
dated March 6, 19/9.
The review included:
documentation; truck placarding; isotopic
determination review; storage area review; and the performance
of independent radiation intensity measurements.
(1) Shipment
The following radioactive waste shirnents were reviewed:
Shipment No.
Date
Item
Total (mci)
79-75
7/18/79
U-l Trash
109.772
148 drums
79-76
7/18/79
Filter
0.006
79-77
7/18/79
Laundry
5.97
79 drums
79-78
7/20/79
Laundry
7.60
72 drums
79-79
7/24/79
RCS Liquid
3.60
79-80
7/25/79
Laundry
11.666
76 drums
79-81
7/30/79
Charcoal
0.080
Sample
79-82
7/31/79
RCS Liquid
13.28
79-83
8/1/79
Laundry
15.63
144 drums
79-63
8/7/79
U-2 Trash
3440.0
157 drums
79-86
8/8/79
Liquid
0.036
Sample
79-87
8/9/79
Liquid
.0992
Sample
79-88
8/9/79
Laundry
8,53
74 drums
79-89
8/14/79
HEPA Filters
3.812
No unacceptable conditions were identified in the above
shipments.
.
.
11
The licensee has revised the conversion factors of curie
estimates for shipments of packaged radioactive material.
The original factors, delineated in procedure 1620,
presented a method whereby curie estimates could be made
by utilizing a curie / rem conversion factor and a contact
gamma doserate of the package. This method however did
not address beta activity determination of the package.
Preliminary review of the revised conversion factors
indicate a possible underestimation of total curie
content.
(2)
Storage of Solid Radioactive Waste
Inspector tours of solid radioactive waste storage areas
identified one Significant Inpsection Finding. The item,
failure to label a radioactive materials storage area, is
appended to this report as Significant Inpsection Finding
Nos. 289/79-18-02; 320/79-22-07.
b.
Posting and Area Control
Tours of controlled and noncontrolled areas were made to
verify licensee compliance with the requirements of 10 CFR 20.203, " Caution signs, labels, signals and controls", Technical Specification Section 6.12, "High Radiation Area" and Station
Health Physics Procedure 1610, Revision 7, " Establishing and
Posting Areas", dated September 30, 1977.
The area tours and the performance of independent radiation
intensity measurements identified the following Significant
Inspection Findings which are appended to this inspection
report:
Number
Item
Date Identified
320/79-22-04
Failure to Post, Barricade
7/22/79
and/or Control (>lR/hr)
Access to High Radiation
Areas
320/79-22-05
Failure to Post, Barricade
8/5/79
and/or Control (>1R/hr)
Access to High Radiation
Areas
The licensee has, in a letter dated August 6,1979, conmitted
to the review and revision of those procedures dealing with
the control of High Radiation Areas.
The revised procedures
will include:
1) specific steps for the control of High
Radiation Area access 2) a surveillance program for identifi-
cation of new High Radiation Areas and 3) a surveillance
program to ensure all High Radiation Areas are properly
controlled.
.
.
12
c.
Radioactive and Contaminated Material Control
Radioactive and contaminated materials control was reviewed
for compliance with the requirements of 10 CFR 20.203 (f)
" Containers" and Station Health Physics Procedure 1682,
Revision 2, " Control of Contaminated Tools, Equipment and
Material", dated April 28, 1977.
The review identified one significant inspection finding. The
finding, relating to control of radioactive and contaminated
material, is appended to this inspection report as Significant
Inspection Finding No. 289/79-18-01; 320/79-22-06.
d.
Radioactive Effluent Releases
c
(1)
Liquid Effluent Releases
Radioactive liquid effluent releases from the plant were
reviewed against the following:
-- 10 CFR 20.106, " Radioactivity in effluents to
unrestricted areas".
-- Station Health Physics Procedure 1621.2, Revison 4,
" Releasing Radioactive Liquid Waste from Unit 2",
dated Jaunary 5, 1979.
-- Special Operating Procedure, S0P No.Z33, Revision 2,
" Water Sump Discharges to IWTS and IWFS", dated
May 18, 1979.
-- Special Operating Procedure, S0P No. Z51, Revision 4,
dated August 14, 1979.
The licensee performs gama spectroscopic analysis of
liquid waste prior to its release from the site.
Based
on inspector review of the analysis, the follcwing
Significant Inspection Findings were identified and are
appended to this report:
Number
Item
Date Identified
'
79-22-12
Failure to Perform Gross
7/20/79
79-18-03
Beta Analysis
79-22-13
Failure to Perform Gross
7/27/79
79-18-04
Beta Analysis
(2) Gaseous and Particulate Effluent Releases
The licensee maintains a supplemental Vent Radiation
Monitoring System to monitor gaseous and particulate
effluent releases from Unit 2.
,
.
13
The system operation was reviewed with respect to the
following:
10 CDR 20.106, " Radioactivity in Effluent to Unrestricted
--
Areas".
Technical Specifications, Appendix B, Section
--
2.1.2., Gaseous Effluents
No unacceptable conditions or significant discrepancies
were identified.
e.
Respiratory Protection
The licensee utilizes the service air system as a source of
breathing air.
On July 30 through August 7,1979; the licensee placed this
system in service as a source of breathing air to specific
work areas of the 281' el of the Fuel Handling Building.
A review of the system utilization was performed. The review
encompassed the requirements of Regulatory Guide 8.15, " Acceptable
Programs for Respiratory Protection".
Based on the review, one Significant Inspection Finding was
identified and is appended to this report as No. 320/79-22-08.
f.
Counting Equipment.
The calibration of licensee radiation counting instrumentation
is performed by a calibration contractor. As a result of beta
contamination identified in smear and air sample results, the
licensee's beta detection and counting instrumentation was
reviewed.
The review encompassed:
(1) use of NBS traceable
calibration sources, (2) use of established and approved
calibration procedures, (3) use of established and approved
operation procedures, and (4) the comparison of licensee
results with those obtained during independent calibration
determinations using calibrated sources obtained from national
laboratories.
Based on the above review, the following Significant Inspection
Findings were identified and are appended to this report:
Number
Item
Date Identified
79-22-09
Calibration and Operation
7/19/79
Deficiencies of Air Sample
and Proportional Counters
79-22-10
Inaccurate Calibration of
7/26/79
Friskers and Smear Counters
_
-
.
14
Number
Item
Date Identified
,
79-22-11
Inaccurate Cs-137 Counting
8/10/79
Efficiencies for Licensee
Proportional Counters
(Contractor Supplied)
.
g.
Augmented Systems
.
The licensee has retained the services of a contractor to
provide for decontamination of small metalic objects (i.e.,
tools,pipesections,etc.).
Prior to initial operation of
the facility, review of facility design, contamination control,
.
. air monitoring, ventilation system design and radioactive
material control was conducted on July 23, 1979.
Minor discrepanices were identified to the licensee. Acceptable
corrective action was completed prior to facility operation.
l
The discrepancies and corrective action taken were as follows:
'
No ventilation was provided in area of initial contami-
--
,
nated material handling. As corrective action, the
'
licensee contractor installed a table with hood where
'
contaminated material will be handled initially.
permit regulation of air flow.
Total exhaust flow rate from the facility was measured to
--
be 560 cfm.
As corrective action, the licensee con-
'
'
tractor realigned existing fan and motor system.
Exhaust
flow rate after realignment exceeded 2,000 cfm.
h.
Plant Tours
Tours were made of both controlled and noncontrolled areas to
r
examine:
access control; personnel frisking; use of survey
meters; adherence to Radiation Work Permit (RWP) requirements
and proper use of respiratory protection equipment.
No unacceptable or condition or significant discrepanices were
identified.
7.
EPICOR II Preoperational Status
The following items were identified during a preoperational review
of the EPICOR II system and procedures and have been discussed with
licensee representatives.
The present CCB operating procedures do not contain a definition
--
of normal operating limits which identify proper operation of
the ventilation system moisture separator, preheater, HEPA
filters and charcoal absorbers. Operating limits for these
-
.
15
paramters will be identified during preoperational testing'and
initial operation of the ventilation system and then incorpo-
rated in a subsequent revision to the Vent System Procedures
(OP 2104-5.16).
Drip pans for CAP GUN PUMPS ALC-P-1, 2, 3, 4 have drain
--
connections which will not drain water to less than 1/2 inch
in the pan and can become a significant radiation source.
Resolution has not been determined.
Drain lines from prefilter/demin pits will leave 1/4 inch of
--
water standing in cavity (same concern as above).
Resolution
has not been determined.
Instrument cables to radiation detectors in prefilter/demin
--
pits need to be tied down/ protected from damage (apparently
has been pinched by moveable ladder leaning on them).
Adequacy of the vent system radiation monitor (ALC-RE-18)
--
sample lines with respect to number of bends, discharge point,
etc. needs to be reviewed.
Need to incorporate a flow meter conversion chart for ALC-FE-17
--
in the operating procedure for the vent system to allow
reading of meter over expected range of operation.
The above items along with system procedural deficiencies were
discussed with licensee representatives.
Resolution of these items
will be followed by the NRC:TMI Support Staff (320/79-22-14).
8.
Exit Interviews
Meetings were held with licensee management to discuss inspection
,
findings and concerns as noted below:
a.
Meeting on August 23, 1979
Licensee Representatives
R. Arnold, Corporation Vice President-Generation, General
Public Utilities Service Manager - TMI Site Operation
R. Dubiel, Supervisor of Radiation Protection and Chemistry
D. Limroth, Superintendent, Administrative / Technical Support
'
I. Seybold, Supervisory Dosimetry
C. Wiblin, Supervisory Respiratory Protection
NRC Representatives
i
J. Collins, Deputy Director, TMI Support
H. Crocker, Chief, TMI Resident Office
D. Neely, Lead Radiation Specialist
f
-
.
16
Items concerning licensee immediate actions to NRC concerns,
contained in a letter.from J. Herbein to B. Grier, dated July
18, 1979, were discussed.
b.
Meeting on August 22, 1979
Licensee Reoresentatives
R. Dubiel, Supervisor of Radiation Protection and Chemistry
J. Herbein, Vice President-Generation, Metropolitan Edison
Company
D. Limroth, Superintendent, Administrative / Technical Support
J. Logan, Unit 2 Superintendent
J. Seelinger, Unit 1 Superintendent
NRC Representatives
R. Conte, Reactor Inspector
H. Crocker, Chief, TMI Resident Office
D. Haverkamp, Lead Reactor Operations Inspector
D. Neely, Lead Radiation Specialist
'
The following items were discussed:
Significant Inspection Finding Nos. 320/79-22-01 through
--
13; and,
-
EPICOR II Concerns.
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_ _ _ _ _ _ _
. . _ _ _ _ _
_
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ENCLOS{ IRE (1) to TMI-2 STANDING ORDER NO. 2
-
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.
I
.
79-22-01
SIGNIFICANT INSPECTION FINDING NO
.
Inadequate Administrative Controls for Recovery Special Operating
SHORT TITLE:
Frocedures (K-due)
(Details attached) Summary below:
DESCRIPTION
tio PORC review and subsequent Superintendent /NRC approval on a Revision to the 80P
.l.
Diesel Operating Procedures.
2.
Procedure. implementation problem not being formally identified.
handwritten copies of procedures (with cross-outs / changes) make pre-approval
J.
Uriginal
anc post approval changes indistinguishable.
'
4.
It appears post-approval cnanges were not reviewed ano approvea.
due cancel tation instructions are not always rol towec.
a.
This reoresents a failure to fulfill 10 CFR 50 Accendix B Criterion VI requirements for
Control of Documents.
IDENTIFYING
LICENSEE REP.
NOTIFICATION
ACCOMPLISHED BY
NRC OFFICIAL
NOTIFIED
~
R. J. Conte % %
Er
SIGNATURE
R. J. Conte nh
_11. Bezilla
R. J. Conte
V
NAME
R. J. Conte
v
TITLE
Reactor Inspector
PORC: Administrator
Reactor Inspector
DATE/ TIME
//12//9 4:00 p.m.
_
__ - ) p-
~
//l///9
10:00 a.m.
,
LICENSEE ACTION TAKEN:'
VERIFICATION.DATE/ TIME 7/31/79 6:00 p.m.
.
A licensee audit of the Control Room R-SOP file was conducted 'sith the following actions
taken:
'
was
-- item i aucve was contirnied anc tne previotisTy~alfproved revision (nevision i)
'
(
reinstaceo in r1te.
Item 2, the specific problem (Missing indicators for BOP Diesel) has been identified
--
to licensee engineering staff who are in consultation with vendor for resolution.
Items 3 & 4, other than that addressed above, no post approval changes were made with-
--
out proper review and approval. Furtner, all effective copies have been (cont, see
Verified by: R.J. Conte, Reactor Inspection (per sampling basis) pi g n
attached)
Name/ Title and Signature
\\J
'
Disposition Recommendation
.
t
/XX /
Document in Inspection Report.
/
/
Additional Enforcement Action because of inadequate licensee action.
/
/
Cancel. Does not warrant inspection documentation.
/h/
Carry as outstanding item for further inspection.
0 1/f f
l
D
u m e=
,w_
p
D. Haverkamp 8/1/79
.
Disposition
Af A A
A M
/L
f
ker
Chief, IE Resident Office, THI-2
8/1/79
Date
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_
_ . _ _
_
_
_
_ _ _
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.
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,2
.
Significant Inspection Finding No 79-22-01 (CONT)
,
.:
.
-
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Description (cont)-
..
'
--
.
.
A.
References
-
,
,
'
l.
Control Room Copy of Recovery Special Operating Procedures (R-SOP) Binder.
2.
SOP-2-79-R-14, Revision 2, June 20,1979, BOP Diesel Generator (DG-A) Gray
and Auxiliaries Panel.
3.
SOP-2-79-R-15, Revision 2, June 20,1979, 80P Diesel Generator (DG-B)
White and Auxiliaries Panel.
B.
Details
1.
Revision 2 to SOP-2-79-R14 and 15 did not have indication of PORC
.
review and subsequent Superintendent /IIRC approval. The associated change
request fann was partially completed. The revision added parameters
to be monitored on the data sheet attached to the procedure.
2.
Although the Data Sheet (addressed above) requires that Crankcase
Pressure and Exhaust Temperature be recorded, instruments to measure these
parameters do not appear to exist. This was based on observation by the
inspector and discussion with the licensee's operator.
(It is not clear whether
or not these parameters are needed to be monitored for the safe operation
of the equipment.)
Further, it appears that these instruments had not been installed
during construction.or initial operation testing of the systems (May 1979).
This 50P was implemented on several occasions and no formal operator
identification of the problem was made.
3. _0riginal handwritten copies of R-SOP procedures (with cross-cuts / changes)
are on file in the Control Room with pre-approval and post-approval changes
being indistinguishable.
In 18 of 32 effective procedures the original was
on file, and in 8 of the 18 cases, significant technical changes (e.g., valve
'
position changes, step reversals, etc.) were noted. This applies to
S0P-2-79-R 1, 2, 12, 17, 19, 22, 29 and 37.
4.
Of the remaining,14 procedures which were not. originals, 5 had technical
changes with no documentation of appropriate review and approval.
It
appears these were post-approval changes.
This applies to SOP-2-79-R-3,10,16, 32 and 38.
Further, in 2 other cases, extraneous marks, notes, questions were
noted on the procedure. This applies to SOP-2-79-R 14 and 38.
l
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,
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a'
3
Significant Inspection Finding fio 79-22-01 (cent)
'
5.
It does not appear cancellation instruction for SOP's (on cover page
of each procedure) are always being followed.
In 8 of 32 effective procedures
'
cancellation instructions were "Upon completion of procedure" or " test".
Some of these tests were issued mid-May 1979 and they appear to be no longer
applicable yet they are still on file. This applies to SOP-2-79-R-5, 12,
,
13, 17, 16, 19, 22 and 24.
Further in three procedures on file in the control room, data is
>
completed on the file copy. This precludes using the file copy to generate
t
a working copy for test records. This applies to S0P-2-79-R 13, 32 and 36.
i
Licensee action _Eulen (cont)
photostated so that post approval change can be identified.
'
-- Item 5, outdated 50P's have been cancelled and removed from file.
In a separate memo, the licensee representative indicated that once Racovery
t
TS are issued a " concrete format for procedure review and approval....will
be clearly defined" Item 2 and Recovery Admin Controls will be followed.
L
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ENCLOSURE (1) to TMI-2 STANDING ORDER NO. 2
-
,
i
f
.
SIGNIFICANT INSPECTION FINDING NO 79-22-02
f
Adequacy of fire protection in Diesel Building (Class IE)
SHORT TITLE:
and Cable Spreaoing Room
-
.
,
,
DESCRIFIION
'
l.
Five fire doors blocked open but required to be keot closed (for access to
A & D Diesel and between rooms)
2.
All portable fire extinguishers were overdue for routine checks in Diesel areas.
3.
Excessive oil leakage for Diesel 1 A
4.
Excessive combustible material in Cable Spreading Room with no hourly fire
!
watch patrol (AP 1034)
License Commitments - See attached
IDENIIFYING
LICENSEE REP.
NCIIFICATION
NOTIFIED
ECOMPLISED:3 IiY
AtRCJdICIAL
/
SIGNATURE
MM 4/ -
-f
_
_Xr
~
-C M t'd M d
NAME
) Eric K. bwanson/
lom U'Lonnor Ext. 236
M . b. Ko t taz /
Keactor inspector
,
TITLE
KeacLar inspecLar
~
same as Detore
,
w --
DATE/ TIME
//ia//y - 440u
VERIFICATION.DATE/ TINE 8/l/79 - 2400
'
LICEN3EE ACTION TAKEN:
.
Door between diesels were locked, doors' closed, hourly surveillarice initiated.
1.
-
-
2.
All portable fire extinguishers were checked for July,1979.
3.
Excessive oil leakage was corrected.
!
4.
runount or comDustible material in Cable bpreading Room was establisned at
an acceptacle level.
.
/
?
/
O2/LL- A
Verifisd by%E." T. Chow, Vgactor Inspector
[Name/TitleandSignature
'
Disposition Recommendation
,
i
!
/^ /
Document in Inspection Report.
o
/
/
Additional Enforcement Action because of inadequate licensee action.
/ /
Cancel. Does not warrant inspection documentation.
/ s/
Carry as outstanding item for further inspectiong
nn/ f/
r7
v kamp
Disposition
As stated
M&0- , /
k
c,/ /
W' C
g
'
Chief, IE Resident Office, TMI-2
i
R/?f70
Date
i
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4
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.
i~ kNCLOSURE (1) en TMI-2 STANDING ORDER NO. 2
-
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t
SIGNIFICANT INSFECTION FINDINC NO
79-22-03
.
5,
,
SHORT TITLE:
Adequacy for Operational Preparedness for Balance of Plant
.
(B0P) Diesels-
-
.
.
.
,
.
.
DESCRIPTION
uuring tne review of this system from August 9 - 17, 1979, severai questions
were raised on the adequacy of the program for making the buP U1esels operacionai
.
in the tollowing areas:
--Uperator training (including Ene implementation or acministrative concruis
!
for orocedures)
'
l
--Procedure orecaration to reflect desian and as built conditions.
Specific examDies of shortcominas in these areas are attached.
IDENIIFYING
LICENSEE REP.
NOIIFICATION
NRC OFFICIAL
N u u r J.t.u
ACCOMPLISHED BY
SIGNATURE
HNLA
_
_
>G--
~
- f 1Kh
NAME
D. Price /R. Conte
J. Chewastzk/ i.Krailling
R. Js Conte
Reactor Inspector
TITLE
Heactor Inspector
Shif t Supervisor / Engineer ~
August 13, 19/9/1100
DATE/ TIME
Aug. 9-17, 19/9
-^'
'
LICENSEE ACTION TAKEN:
VERIFICATION _DATE/ TIME
-
.
1.
Procedural problems have been corrected in subsequent revisions cu
both Uperating Procedures for the Caray and Miite biesels.
-
"'"-
~
'
2.
Fire Protection discrepancies are currently under review by tne licensee.
7
\\
.
Verified by:
10 . Mrv
P .1 C , A t
P , , , t ,, . T x w,,
'
_
.
v
Name/ Title >and Signature
Disposition Reconsnendation
,
',
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i
!
@
Document in Inspection Report.
/ /
Additional Enforcement Action because of inadequate licensee action.
/
/
Cancel. Does not warrant inspection documentation.
/X'/
Carry as outstand'ing item for further inspection.
'
D
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/.
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YY
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.
LeadOpsorHPIn/pector
.
,
Disposition
.
M
Chief, I F Resident Office, THI-2
'
Date
!
.
__.
. __L
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a
.
,
.
.
AttacNnent 1
'
DESCRIPTION
'
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'
A.
The following observations were nide during the performance of the
operational test on August 9,1979 of the Gray Diesel, R-2-79-15,
Balance.of Plant (B0P) DG-A (Gray) Diesel and Auxiliaries Operating
Procedure, dated August 9,1979.
1.
Sections 4.2.1 and 4.2.2 require that fuel oil day tank be at least
200 gallons and the storage tank for the Gray system be at least 3500
gallons. The recorded values were 175 gallons and 2750 gallons
respectively.
The procedure was completed with no formal change to the
procedure and/or identification of the problem to management.
It was later determined (that same day) that the White diesel was run
without meeting the required fuel storage tank limit as specified in
the procedure. Several days later the tank curve for this system was found
to be in error in a conservative direction.
In actuality the procedural
limit (which reflects proposed T.S. limits) was met.
2.
On August 9',1979 both the White and Gray Diesel .were tes'ted simultaneously.
This is contrary to Revision 1 of TMI-2 Criteria for Loss of ~0ff Site 80P
Electrical Power.
Both operating procedures did not preclude simultaneous
testing.
3.
Section 4.1.1.3 of the Gray Diesel Operating procedure states the
!
operator was to verify immersion heater control of jacket water temperature
between 125 F and 1550 F.
The recorded value on startup lwas 1200 F which
came up to the specified range. The procedure was completed.
It was later determined by the licensee representative in consultation
with the vendor, that controlling temperature was set for 1150 F to 1550 F.
,
4.
Section 4.3.11.5 required that the operator verify a current of
approximately 434 amperes with a load of 2500 KW, 4160 volts, 60 Hz. The
actual indication was 343 amperes.
It was later determined that the 434 amperes value. !was a maximum limit.
5.
Section 3.1 required the check of instrument root valve position,.
The
operator initially indicated that they were inaccessible and used
indication on one gauge as verification of valve position.
The operator
later (dur.ing the conduct of the startup procedure) consulted a.n ,
engineer who directed the proper valves to be checked which were accessible.
6.
The data sheet requires a check of level in the Fu'el Oil Return
-
Sight
Glass and Fuel Oil Bypass Sight Glass. The operator claimed
they didn't exist. .The procedure was completed wi,thout recording the
value.s. . The Sight . Glasses do exist.
'
'B.
The cover memorandum for Revision 2 to TMI-2 Criteria for Los~s' of Off-Site
80P Electrical Power states that Revision 2 incorporates as built fire
protection for the Gray and White Diesel. Based on actual observation tha
following discrepancies were noted with respect to Revision 2:
-
ame
-
-
.s
,'
.
-
- . . .
Attachement 1
.
2
.
1.
Oike for the White diesel storage tank is not completed.
.
.
2.
No fire detection devices exist in diesel or storage areas.
'
3.
Only one fire extinguisher is in the White Diesel enclosure
'
making it inaccessible with fire inside the enclosure.
-
4.
A local fire hydrant with hose storage is not addressed in the
criteria.
C.
During a test of the Gray Diesel on August 17,1979 (10:00 p.m.) it
was observed that the operator waited until completion of the procedure
to initial off completed steps. When the procedure was signed off,.
!
3 lines were left blank and one "large" initial was to cover several
lines of the valve line-up sheets (Attachment )). The blank s,teps were
3. 5, 4.4.1.1, 4.4.1. 2.
This is contre.ry to AP1001 paragraph 3.8.5.a,
4
which requires that plant operating procedures shall be followed and
signed off step-by-step, and paragraph 3.8.5.f which states that Special
Operating Procedures are subject to the same level of control and approval
4
as operating procedures.
!
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"': i.cstf7I (IT to TF1-2 ST!JC:NC OT.DET. NO. 2
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/79-22-04
"
SIGNIFICANT INSPECTION FINDING NO
SHORT TITLE:
High Radiation Area Control / Posting and Barricading
.
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DESCRIPTION
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See attached.
.. -
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IDENTIFYING
LICENSEE REF.
NOIIFICATION
--
NRC OFFICIAL
NOTIFIED
~ACCOMPl.IS}-TD EY
' i - Ja n u, ,L.
l.AJ
'
-
~
SIGNATUREIV ArmL, fx1
--
NAME
l'
R. J. h45ett.
l
Paul Schaule
(l
~'R'. J. Eferft't
ll
Radiation Specialist
-
TITLE
i
Radiation Specialist
i
NSS H.P. Supervisor - ll
7/23/79 @l530
} }M-
DATE/ TIME l
7/22/79 @l500
{:
=
-
.
,
LICENSEE ACTION TA}2N:
VERIFICATION 2 ATE / TIME
'
Per ' discussions with Schaule, the licensee will :
l*
Place lead blankets in area near containment wall.
2.
Place lead wall and locks to be utilized at valve room outside
make up tank.
3.
Fabricate door to control access to cast corridor of FHB.
.
Verified by:
Name/ Title and Signature
Disposition Reco=endation
3
ACX /
Document in ' Inspection Report.
/
/
Additional Inf orc ement Action because of inadequate licensee action.
/
/
Cancel. Does not wa rr,,nt inspection documentation.
/XX /
Carry as outstanding item for further inspection.
/
/
.- .
Q
l(.-7
'
.R.
Neely
.
,
<
Disnosttion
x/
A0
A
&VfW ^ '
H.W. Crocker
Chief , IE Resident Office,"I'MI-2
?&f
'
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Date
--
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n
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f
e
1
4
"
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Description
The following High Radiation areas, emanated whole body dose rates greater
than 100 mnem/hr and were either not controlled (i.e., locked or manned in
^
the case of those areas greater than 1000 mrem /hr) and/or were not posted
and barricaded as required by Technical Specification 6.12 and 10 CFR 20.203(c)
4
Date
Area
Whole Body Dose Rate (mrem /hr)
7/22/79
Unit 2 - Aux. Bldg
3000
328'el - Concentrated
(access not controlled)
Waste Tank Cell
1
!
305'el - Area Near
2000
HP-R-227
(decess not controlled)
'
281'el - Open Elevator
200-300
i
Shaft
(not posted or barricaded)
. - .
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7""" 05 t~.I
/I S te T.0-2 STA'Q!?;O ORDEE N:). 2
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SIGNIFICANTINSPECTIONFINDINON0h9-22-05
SHORT TITLE:
High Radiation Area Control / Posting and Barricading
.
. . .
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. #'US..
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P:'
DESCRIPTION
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T *-> >
~2 C'
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See attached.
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9
3
o
g
IDENTIFYING
LICENSEE REP.
NCIIFICATION
---
NRC OFFICIltL
NOTIFIED
'ACCO."F"ISEED BY
SIGNATURE l
10 d,M i .1,. _ [,t
I _ t-
X
' -Myt . L .h
i
gug
l l ' Blaine Jiuf ry
P. Schaule
l BlainTe @ riff
TITLE
'l l
Radiation Specialist
NSS H.P. Supervisor
l Radiation Specialist
-
DATE/TIMEi!
W"
ll
- -- Er
ll
8/5/79
,
.
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LICENSEE: ACTION Tal'EN:
VERIFICATION 2 ATE /IIME
Licensee to secure,. post and barricade as necessary
.
I
verified by:
Name/ Title and Signature
Disnosition Beco=nendation
'
-
/W
Doct=nent in Inspection Report.
/
/
Additional Enforce:nent Action because of inadequate licensee action.
/
/
-Canc el . Does not warrant inspection documentation.
M
Carry as outstanding it e= f or further inspection.
/
/
. , ,
,
.
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.
i
Disnosition
M/I-,/MJ
/L
^'
W
oc
(
'
Chief,
E Resident Of fice, TMI-2
of-
/ &
F '7/ J 7
f
'Df t e'
/
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_
.t...._-
_
..
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,
.
re -
Description
The following High Radiation Areas, emanated whole body dose rates greater
than 100 mrem /hr and were either not controlled (i.e., locked or manned in
the case of those areas greater than 1000 mrem /hr) and/or were not posted
and barricaded as required by Technical Specification 6.12 and 10 CBR 20.203(c) .
Date
Area
Whole Body Dose Rate (mrem /hr)
8/4/79
Unit 2 Aux. Bldg.
4000
328'el. 4 Aux. Bldg
(access not controlled)
Filter Room
305'el. - High Radiation
7000
area near pipe
(not posted and not
at entrance to
barricaded)
MU Tank Room
281'el. - Aux. Bldg. Sump
4000
Filter Cell
(access not controlled)
__._
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S2 CNITICA1;T INSFECTION FII; DING 1;o 79-22-06
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SHORT TITLE: Contaminated Haterial Control
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DESCRIPIION
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nn inspector tour on 7/23/79 identified 6 semi-trailers located 'near tiie Uffi't'l Raartnr
Buiioing equipment Hatch.
Ine trailers contained lumber and equipment and were costed
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rouivoccive. n raciation/ contamination survey performed by the licensee health ohvsics
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congactor,1ndicated radiation dose rates and contamination up to 5 mR/hr and s 1000
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upiiy suu cmc respectively on the uncontrolled radioactive materi als. The licensee did Hnt
nave any means to assure that the radioactive material (i .e. lumber. eauinment. prc )
were not used in an uncontrolled area (i.e. c19an araae)
Tha ahnun renresen.tr fai hr
to adhere to Station Heal th Physics Procedure 16R2. "rnntrn1 nf cnntn.,innted teels,
equipment and materials, Rev. 2 dated 4/28/77 Section 5.2.
IDEhIIFYING
LICENSEE REP.
NCIIFICATION
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NRC OEF1CIAL
1;OTI- IED
. ACCO.MISHED EY
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SIGNATUREi- MORA I'd
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pgu, g
51aintifiutiy
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B. Good
BlaineMurrvh
TITLE
l Kauiation dpecia list
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Radiation Specialist
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DATE/ TIME l l //24//9
1600
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7/24/79
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VERIFICATION .DATE/IIME .7/26/79
1400
LIkENSEE : ACTION TAKEN:
nspector review on 7/26/79 noted alTiocks to be installed on above trailers
anu securea t.o prevent unauthorized removal of equipment
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Verified by:
Blaine Murrv. Radiation Snacialiet
/6 Atm /.. b)
Name/ Title and Signature
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Disposition Reco:cendation
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Document in Inspection Report.
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Additional Enf orcement Action because of inadequate licensee action.
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Cancel.
Does not warrant inspection documentation.
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Carry as outstanding item f or further inspection.
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Dianosition
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Chici, IE Resident Office, TMI-2
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Date' ' '
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S2 CNITICANI INSIICTION TIliD1110 1;0 79-22-07
sHORT TITLE:
Improper Posting of Radioactive Material Storage Area
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DESCRI PTION
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itumerous 55-gallon drums . stored on El 305', Unit 1 Turbine Deck were -labeled wi' h
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wnite-i or ye t low-11 iaoeis. Raciation oose rates measureo u.i-2..+ mR/ nr.
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ine crum storage area was not postec as a racioactive materiai area as
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required oy 10 M H zu.zu.s (e) (i),
ine Unit I turoine cecK nas oeen
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utilized as a storage area for low level Unit 2 trasn.
IDEh'TIFYING
LICENSEE REP.
NCIIFICATION
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NRC OFFICIAL
Nuur IED
' ACCOMPLISHED EY
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i - G. L. Troup )10%L 44
SIGNATURE l -
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G. L. Troup'~~
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NAME
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'G 7L . Tri/u p'..~
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M. A. Janowski
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TII1E
.l L Radiation Sdecialist
l Met. i.d Senior H.P. Tech.
Radiation Specialist
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19 July - 1735
DATE/ TIME ll 19 July - 1725
IICENSEE!ACHON TAKEN:
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VERIFICAHON .DATE[IIME
19 July-lh55
The ' area was barricaded with yet low rope and posted with. " Caution -
Haaloactive Materials".
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verified by:
A) F w A #c
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Name/ Title add Siggat'ir e " M
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Disposition Reco==endation
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Document in Inspection Report.
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Additional Enforcement Action because of inadequate licensee action.
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Cancel. Does not warrant inspection documentation.
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Carry as outstanding item f or further inspection.
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Disvosition
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H 'CEici, ~15R e sid ent Office, THI-2
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' 'ETC1.05URE. (1) to TMI-2 STANDING ORDER N0. 2
79-22-08
SIGNIFICANT INSPECTION FINDING N0.
SHORT TITLE:
Failure to utilize breathing air system properly
DESCRI'PTION:
See Attached
' IDENTIFYING
LICENSEE REP.
NOTIFICATION
NRC 0FFICIAL r
NOTIFIED
ACCOMPLISHED BY
SIGNATURE
h ,, L.
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/0P M /
NAME
Nilliam J. Itillsap
Earl Gee
0?neely/W. / Mil l sap
TXTLE
Radiation Specialist
Safetu Supervisor
0 ATE / TIME
8/12/79 /0830
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8/17/79
LICENSEE ACTION TAKEN:
VERIFICATION DATE/ TIME
A technical meeting was held on August 17, 1979 to discuss the licensee's
respiratory protection program witn respect to the above items.
Specific
items included minimum program requirements as specified in Regulatory
Guide 8.15 and the guidance of NUREG-0041.
The licensee indicated the
breathing air system will be audited and an action item list developed.
Verified by:
Name/ Title and Signature
Disposition Recommendation
lX
Document in Inspection Report.
Additional Enforcement Action because of inadequate licensee action.
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Cancel. Does not warrant inspection documentation.
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Carry as outstanding item for further inspection.
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Disposition
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W y v i L, r w wp
H. W. Crocker
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Chief, IE Resident Office, TMI-2
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Attachment 1
DESCRIPTION
The licensee utilized the breathing air system (service air) in support
of work being performed on the 281 ft. elevation of Unit 2 FHB during the
period July 30 thru August 7, 1979. A review of system utilization
indicated the following:
- During the above period, contractor personnel utilized an air supply
manifold in conjunction with full face piece air supplied respiratory
equipment. The face piece was designed to operate properly at 80 psi
however the manifold was providing only 40 psi. Consequently the
proper air flow was not being provided to the user.
The full face piece breathing air regulator used with the manifold
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was found on August 7,1979, to have been modified to allow the
regulator to remain in a fully open position, thus providing full
air flow. The regulator had been jammed open by means of tape.
- As a result of pressure problem identified in MSA manifold, the air
manifold was removed on August 7,1979. The full face piece
respirator was connected via hose directly to the service air sparger.
An in-line filter was placed in the line to remove rust identified
during previous sparger blowdowns. As a result of filter clogging
personnel were not provided air of sufficient quantity on
August 13, 1979 in that personnel suffered loss of adequate breathing
air.
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Attachment 1
FINDINGS
A standard f Source, Sr-90/Y-90 .0034uCi electroplated, was submitted
to the licensee for counting. The results of the counting were
compared against the licensee's standard source, Eberline Cs-137.
The following was noted:
Sr-90/Y-90 Results
(uCi)
Source
Proportional Counter
Eberline Probe
Position
(PC-4)
(H.P.-210)
bare
.0035113%
.0021 + 2.5%
Thru 1 filter
.0021 1 1.8 %
.0020 1 2.5%
Thru 2 filters
.0014_+2%
.0018 1 2.7%
The above indicates a recovery of 62% of true activity for the H.P. 210
probe and 103% for the proportional counter.
The following deficiencies were noted:
1.
The H.P.-210 detector underestimates the total activity by 38%.
2.
The calibration performed by the licensee is not typical of samples
analyzed.
3.
The accuracy of the standard calibration source is questionable
and not traceable to NBS.
4.
There is no management or independent audits of activities in this
area (i.e. submission of standard sources to contractor for counting).
5.
The following procedural deficiencies were noted:
a) No approved calibration procedures are being utilized.
b) No QA/QC controls are implemented.
c) No approved procedures are being utilized for:
1) decay correction,
2) sample handling, 3) counting time determinations, 4) resolving
time corrections and 5) sample activity determinations,
d) No approved procedures are being utilized for additional evaluations
and acceptance criteria of final sample data.
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'NCLOSURS (1) to TMI-2 STANDIf4G ORDER N0. 2
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SIGNIFICANT INSPECTION FINDING NO.
79-22-09
SHORT TITLE:
Calibration and Operation Deficiencies of Air Samp1.e and Proportional
Counters Operated by Licensee Contractor
DESCRIPTION:
a review was made of the calibration, operation, procedures and QC and the adequacy
of equipment used to evaluate airborne concentrations. A standard sample was
suomitted tor counting and the perf ormance evalua ted.
de v le"v 11ncings are noted on
the attached sheet.
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TDMTIFYING
LICENSEE REP.
NOTIFICATION
NRC 0FFICIAL
o
NOTIFIED
ACCOMPLISHED BY
StGNATURE
21(ks , e /w V.n)
X
DAM,&v
NAME
R .' J . Evete t W
D. Limroth/R. Dubiel
'D. 'Neely/d . Everett
TITLE
Radiation Spe'cialist
Met. Ed.
DATE/ TIME
7/19/79
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LICENSEE ACTION TAKEN:
VERIFICATION DATE/ TIME
Meetings were held to address licensee deficiencies in the area of procedures,
quality control, use of NBS traceable sources,
fue meeting nela inalcatea a review
and procedural revision would be conducted to correct the above.
Verified by:
Name/ Title and Signature
Disposition Recommendation
lX
Document in Inspection Report.
Additional Enforcement Action because of inadequate licensee action.
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Cancel.
Does not warrant inspection documentation.
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Carry as outstanding item for further inspection.
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Dispositio_n
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Chief, IE Resident Office, TMI-2
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ENCLOSURE (1) to TMI-2 STANDING ORDER NO. 2
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79-22-10
SIGNIFICpYr INSFECTION FINDING NO
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Inaccurate Calibration of " Friskers" and smear counters
SNORT TITfE:
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DESCRIPTION
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cattorated CS-137 source was used on July 26, 1979 to verify lic'ensee' efficiency
Acalculations tor scalers and " Friskers" using the Eberline H.P. 210 probe
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Based on the etticiency check, a value of 15 to 187.was obtained.
as cetector.
Ine Licensee currently uses .30 to 407..
This results in an underestimation of
accivtcy oy a tactor or approximately 2.
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IDENTIFYING
LICENSEE REF.
NOIIFICATION
ACCOMPLISHED BY
NRC OFFICIAL _
NOTITIED
,
-li O +%A $4/
SIcNATURE
lhe AL.f v F#
'5'.'Ewa1d / /
NAME
~St' eve' EwiYd /f'
R. Jaeobs
Radiation Spe'cialist
Supervisor Rad Services
Radiation Specialist
TITLE
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7/27/79/1000
DATE/ TIME
7/26/79/1000
VERIFICATION.DATE/ TIME
LICENSEE ACTION TAKEN:
Pending 1icensee receipt of NBS' traceable sources, the licensee will
adwints tratively set tne etticiency at the H.P. 210 probe at 157..
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Disposition Recou:mendation
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Document in Inspection Report.
Additional Enforcement Action because of inadequate licensee action.
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Carry as outstanding item for further inspection.
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Disposition
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Chief, IE Resident Office, TMI-2
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ENCLOSURE (I) to TMI-2 STANDING ORDER NO. 2
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SIGNIFICANT INSFECTION FINDING NO
79-22-1l
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Inaccurate CS-137 Counting Efficiencies for Licensee
SHORT TITLE:
Proportional Counters
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DESCRIPTION
On August 4 and 10,1979, a CS-137 source was submitted to the licensee's counting
ine source cocained invi.ia
contractor for counting and subsequent evaluation.
uvuotin3
lab, indicated a 3/-4U2 counting erriciency on nne cont.couturs
national
equipment. The licensee's plated CS-137 source (non-traceable) indicated
u5-707. efficiency. Based on these results, the licensee will under estimate total
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beta activity by a factor of 2.
IDENIIFYING
LICENSEE REP.
NOIIFICATION
NRC OFFICIAL
NOIIFIED
-ACCOMFLISHEDrBY
SIGNATURE
})(hAo le {+
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NAME
'Wrillam /1iifJp
K. i-redricks/0. Limrotn
William MiTisfp ~
TITLE
Radiation Specialist
Met. Ed.
Radiation Specialist
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DATE/ TIME
August 10, 1979
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LICENSEE ACTION TAKEN:
VERIFICATION .DATE/ TIME 10 -
The licensee will administratively set the proportional counter counting
ef ficiency at eu, until sucn time that ttle licensee can obtain an adequate
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coiioracion source.
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Verified by:
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Name/ Title and Signature
Disposition Recommendation
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Document in Inspection Report.
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Additional Enforcement Action because of inadequate licensee action.
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Cancel. Does not warrant inspection documentation.
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Carry as outstanding item for further inspection.
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U. Crocker
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C'..ief, IE Resident Office, TMI-2
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ENCLOSURE (1) to TMI-2 STANDIl1G ORDER NO. 2
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SIGNIFICANT INSPECTION FINDING N0. 79-22-12
SHORT TITLE:
Failure to perfonn gross beta analysis
DESCRIPTION:
A review of isotope data for a pending liquid waste release on July 20, 1979
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(No. 14102) revealed tile presence of Ba-La-140 (20 MiPL).
51nce bd-La- WU are
fission products, this inoicated the possio111ty or unicentitiea oeta
emitters in the 11guld. As a result a gross Deta analysis snoula nave oeen
performed prior to release of tne tank. 51nce the release or tne Waste
Evaporator Condensate Tank was pending, tne inspector orougnt Unis to Ene
attention of licensee representatives who cycled tank back tor treatment.
This is a failure to survey (20.20lb) to meet 20.106.
IDENTIFYING
LICENSEE REP.
NOTIFICATION
NRC 0FFICIAL e
NOTIFIED
ACCOMPLISHED BY
SIGNATURE
A Emh L
X
/dgab
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NAME
~5.'C.
Ewaild 0
unit i bnir'.
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twa w
6
T1TLE
Radiation Specialist
dupervisor
Maoiation Specidiist.
DATE/ TIME
//20/79 / 1400
,X
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1640
LICENSEE ACTION TAKEN:
VERIFICATION DATE/ TIME
Licensee is reviewina procedural controls to preclude similar events, as based
on discussions with D. Limroth and R. McGoey on July 23, 1979.
Verified by:
S. Ewald / Radiation Specialist
Name/ Title and Signature
Disposition Recommendation
lX
Document in Inspection Report.
Additional Enforcement Action because of inadequate licensee action.
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Cancel.
Does not warrant inspection documentation.
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Carry as outstanding item for further inspection.
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01sposition
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Chief, IE Resident Office, TMI-2
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'dlCLOSURE (1) to TMI-2 STANDIliG ORDER N0. 2
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SIGNIFICANTINSPECTIONFINDNGNO.
79-22-13
SHORT TITLE:
Failure to perform gross beta analysis
DESCRIPTION:
See attached
' IDENTIFYING
LICENSEE REP.
NOTIFICATION
NRC 0FFICIAL
NOTIFIED
ACCOMPLISHED BY
,
SIGNATURE
dit k' M u L
/. ed
X
/JLIE- m d -
NAME
' S . 'C'. Ewa l d/ ji~
Gary Miller
D. ~R. Neelf
TITLE
Radiation Specialist
Station rianager
Lead Radiation Spec.
DATE/ TIME
7/27/79
1030
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7/27/79
1430
LICENSEE ACTION TAKEN:
VERIFICATION DATE/ TIME
Licensee is analyzing sample for Sr-90. Additional procedures requiring
gross beta analyses of liquid effluent samples will be developed
Verified by:
Name/ Title and Signature
Disposition Recommendation
lX
Document in Inspection Report.
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Additional Enforcement Action because of inadequate licensee action.
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Cancel. Does not warrant inspection documentation.
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Carry as outstanding item for further inspection.
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Disposition
MW/d5
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YCN
Chief, IE Resident Office, TMI-2
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Attachment 1
DESCRIPTION: Failure to perform Gross Beta Analysis.
The licensee halted a liquid release (No. 112) after the inspector brought
it to the licensee's attention that no gross beta analysis of tank contents
had been performed. The Waste Evaporator Condensate Storage Tank B had
been pumped to the river from 0655 to 1505 on July 27, 1979. A gamma
spectrum of the tank contents indicated Ba-La-140 (3.0E-SuCi/cc). A
subsequent beta analysis of tank contents indicated 8.32E-4uCi/cc. The
resulting release to the river was 170% of the instantaneous limit of
10 CFR 20 Appendix B Note 3 b.
For the purposes of 10 CFR 20.106, the
,
concentration may be averaged over one year.
The above indicates licensee failure to survey (10 CFR 20.201 b) to
meet the requirements of 10 CFR 20.106.
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