IR 05000289/1974005
| ML19253B741 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/13/1974 |
| From: | Brickley R, Dante Johnson, Mccabe E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19253B731 | List: |
| References | |
| 50-289-74-05, 50-289-74-5, NUDOCS 7910180725 | |
| Download: ML19253B741 (17) | |
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U.S. ATOMIC ENERGY CO.scilSSION
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l DIRECTORATE OF REGUIATORY OPERATIONS
REGION I
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K0 Inspection Report No:
sn 9.co/76-ns Docket No:
50-289
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Licensee:
Met =qpolitan Edison Company License No:
CPPR-40 Three Mile Island Unit 1 Priority:
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Category:
B1
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Location:
Middletown, Pennsv1vania
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Typ'c of Licensee:
P a, 831 MWe (B&W)
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Type cf Inspection:
Routine
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Dates of Inspection:
February 12-15, 1974 Dates of Previous Inspection:
February 8, 1973
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3//2/7y Reporting Inspector;
W D. F. Johnson, Reactor Inspector'
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Accompanying Inspectors:
8. /V.
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R. H. Brickley, Reactfr Inspector N W. h d
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j puJ.N.Hannon,-Reacto(Inspector'
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Other Accompanying Personnel:
None
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1445 141 Revieued By:
O. @, ( M ht-3/ gg) 7q
t.. L. McLaue, Senior Reactor inspector, deactor Operations Branch
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- i 7-SUMMARY OF FINDINGS
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i Enforcement Action j
None Licensee Ac' tion on Previously Identified Enforcement Matters
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The licensee's corrective action as specified in his letter of response
.ated February 12, 1974 to the violations identified in RO:I letter dated January 17, 1974 and RO Inspection Report No. 50-289/73-25 was reviewed during this inspection. These items are resolved.
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(Details, Paragraph 11)
-1 Design Changes
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None identified
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Unusual Occurrences
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The diaphragm on Condensate Storage Tank COT-1B failed.
(Details,
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Other Sienificant Findines
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A.
Current Findings l.
The Industrial Security Program is not fully implemented.
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(Details, Paragraph 3)
2.
Revision of the E=ergency Procedures is planned.
(Details, Paragraph 2)
3.
The following status of completion was reported tor the Facility l
Procedures Program:
(Details, Paragraph 7)
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% Written % Final Aeproved l
i Operating Procedures 100
j Emergency Procedures 100 100
Administrative Procedures 100
Surveillance Test and Calibration Procedures
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Corrective Maintenance Procedures
(Mechanical)
91
Alarm Procedures
98
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% Written % Final Approved
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Health Physics Procedures
85 Chemistry Procedures 100 100 Reactor Engineering Procedures 100 100
4.
Station Organization was reviewed.
(Details, Paragraph 5)
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6.
Compliance with 10 CFR 19 was reviewed.
(Details, Paragraph 9)
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6.
QA audits of initial fuel receipt, inspection, and storage were reviewed.
(Details, Paragraph 10)
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7.
Westinghouse W-2 switch and DB-50 reactor trip breakers status was reviewed.
(Details, Paragraph 13)
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B.
Status of Previousiv Reported Unreso'lved Itecs
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l The following items are resolved.
1.
Reactor Trip Procedure.
(Details, Paragraph 8.a)
2.
Control Room Fire Procedure.
(Details, Paragraph 8.b)
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3.
Decay Heat and Nuclear Service Water Systems Procedures.
(Details, Paragraph 8.c)
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4.
Condensate Storage Tank Diaphragm Inspections.
(Details, Patagraph 8.d)
5.
Reactor Vessel Closure Head Stud Corrosien Protection.
(Details,
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Paragraph 8.e)
6.
Action Control System.
(Details, Paragraph 8.f)
7.
Initial Startup QA Audit Schedule.
(Details, Paragraph 8.g)
l 8.
Calibration Data Retrieval.
(Details, Paragraph 8.h)
j 9.
Test Equipment Control Indoctrination.
(Details, Paragraph 8.1)
l 10.
Equipment History Cards.
(Details, Paragraph 8.j)
l 11.
Emergency Flood Control Procedure.
(Details, Paragraph 8.k)
- i 12.
Station Maintenance Implementation and Control Procedure.
(Details, Paragraph 8.1)
13.
Health Physics Procedure 1630.
(Details, Paragraph 8.m)
14.
Operator Determination of Boron Concentration.
(Details,
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Paragraph 8.n)
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15.
Refueling Procedure.
(Details, Paragraph 8.o)
l 16.
Initial Fueling Instructions and Procedures.
(Details, i
Paragraph 12)
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Manacement Interview The management interview was held at the site on February 15,'1974.
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Personnel Attending
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Metropolitan Edison Cocoany
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Mr. T. S. Baer, Station Engineer Mr. J. J. Colitz, Station Engineer Mr. J. R. Floyd, Supervisor, Operations
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Mr. J. G. Herbein, Station Superintendent
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Mr. J. F. Hilbish, Proj ect Engineer Mr. J. P. O'Hanlon, Nuclear Engineer Mr. W. E. Potts, QC Supervisor Mr. M. A. Shatto, PORC Secretary
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Mr. R. L. Su=mers, Plant Engineer
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General Public Utilities Service Corporation
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Mr. J. J. Barton, Test Manager Mr. S. Levin, Project Engineer Mr. M. J. Stromberg, Site Auditor Mr. W. T. Sturgeon, QA Specialist
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The following summarizes items discussed.
A.
Industrial Security Plan.
(Details, Paragraph 3)
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B.
Emergency Procedures.
(Details, Paragraph 2)
C.
Facility Procedures Program Status.
(Details, Paragraph 7)
D.
Tour of Facilit.y.
(Details, Paragraph 6)
E.
Compliance with 10 CFR 19.
(Details, Paragraph 9)
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F.
QA audits of initial fuel receipt, inspection, and storage.
(Details, Paragraph 10)
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Actions on previous enforcement items.
(Details, Paragraph 11)
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Procedures' provided for R0:I's review.
(Details, Paragraph 4)
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Initial fueling instructions and procedures.
(Details, Paragraph 12)
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Actions on previously unresolved items.
(Details, Paragraph 8)
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f DETAILS
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1.
Persons Contacted
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Metrocolitan Edison Ccmpany
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Mr. T. S. Baer, Station Engineer
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Mr. K. E. Beale, Radiation Protection Mr. E. E. Bulmer, Engineer Mr. J. J. Colitz, Station Engineer Mr. R. Deakin, Radiation Protection Supervisor
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Mr. J. R. Floyd, Operations Supervisor Mr. B. C. Getty, Project Engineer Mr. C. E. Hartman, Engineer Mr. J. G. Herbein, Station Superintendent
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Mr. J. F. Hilbish, Project Engineer
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Mr. R. P. Miller, Engineer Mr. J. P. O'Hanlon, Nuclear Engineer
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Mr. D. Pilsitz, Control Roca Operator Mr. J. F. Peters, Office Supervisor S.
Mr. R. H. Porter, Shift Supervisor Mr. W. E. Potts, QC Supervisor Mr. W. S. Poyck, Staff Specialist
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Mr. R.,A. Rice, Security Specialist Mr. M. A. Shatts, PORC Secretary Mr. R. L. Summers, Plant Engineer
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Mr. R. W. Zechman, Training Specialist l
General Public Utilities Services Corporation l
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Mr. J. J. Barton, Test Manager l
Mr. R. Fonti, QA Specialist Mr. S. Levin, Project Engineer
- I Mr. J. Renshaw, Project Engineer
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Mr. M. J. Stromberg, Site Auditor Mr. W. T. Sturgeon, QA Specialist 2.
Emergencv* Procedures
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Emernancy procedures were reviewed, with special attention placed
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upon identification of plant limits involved. The licensee agreed j
to review the procedures and, where necessary, to include provisions for investigating the cause of the emergency, to ensure that suffi-
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l cient communications are provided to plant personnel, and to provide
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a table of contents.
The licensee agreed to revise 15 cmcrgency i
procedures based on the inspector's comments, with inspector comments
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on 2 other procedures to be taken into consideration for future
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resolution.
Subparagraphs 2.a through 2.o following identify com-ments to be incorporated.
Subparagraphs 2.p and 2.q contain com-ments to be considered.
a.
120'2-02, Station Blackout, 10/13/73, Rev. 0
(1) Alarms and changes in system operations which will aid in identifying the emergency are not identified.
(2)
The cooldown curve for natural circulation cooldowns
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(Step 2.2.B.12) was not referenced.
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b.
1202-02A, Station Blackout with Loss of Diesel Generators, 10/13/73, Rev. 0
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(1)
No steps are prescribed for action to be raken in the event diesel generators do not start in Step 2A.2.B.4.
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(2) The procedure for restoring gas pressure in Step 2A.3.5.g
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was not identified.
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c.
1202-04, Reactor Trip, 9/22/73, Rev. O
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Step 4.2.a requires operator interpretation in that one sentence states that all rods with the. exception of Group 8 will be on the bottom and the next sentence inters that all rods will be on the
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bottom.
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d.
1202-06, Loss of RC/RCS Pressure, 10/20 /73, Rev. O I
(1) Manual actions the operator must take are not described in l
Step A.6.2.B.1.
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(2)
Preci.ae limits are not identified in Step A.6.2.B.4, Step A.6.3.B.4 and Step B.6.2.5.
(3)
The reason for referencing the Loss of Decay Heat Removal l
System Emergency Procedure in Step A.6.3.B was not identified.
(4) The reference to emergency plans and procedures in Step A.6.3.B.8 was not specific.
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(5) Step B.6.3.C does not include radiation levels.
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1202-08, Control Rod Drive System Malfunction, 9/22/73, Rev. O
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(1) The note at the bottom of Page 1 does not identify how
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correct overlap is determined.
(2)
Step 8.3A.3f does not identify. when the one hour time j
period commences.
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f.
1202-11, Hich Activity in Reactor Coolant, 10/27/73, Rev. O Step 11.3.8 only considers the case where the reactor has been i
reduced in power.
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g.
1202-12, Excessive Radiation Levels, 10/26/73, Rev. 0 Appendices A, B, and C have not,been entered.
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h.
1202-16, RC Pumo and Motor Emergencies. 9/22/73, Rev. 0
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(1) Precise limits are not identified in Steps 16.1.1.2.a.2
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I and 16.2.1.2.a.2.
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(2) The case where total injection flow is high (> 42 GPM)
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does not appear to be addressed.
(Step 16.1.1.a)
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1.
1202-19, River Water System Malfunction, 7/13/73, Rev. 0 Followup actions are not specified.
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1202-20, Nuclear Services Closed Cocline System, Failure,
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Abnormal, 9/22/73, Rev. 0
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The title indicates that this procedure may belong in 1203 series, Abnormal Conditions.
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1202-24, Steam Supply System Ruoture, 6/8/73. Rev. O I
(1) The procedure does not prescribe steps to verify that the containment is intact.
I (2)
No announcement is required of the operator to alert plant i
personnel of the emergency.
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1.
1202-26, Loss of Steam Generator Feed, 6/29/73, Rev. 0
j (1)
Step 26.2.B.1 does not specify the necessary corrective
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action.
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(2) isrlficationthatanadequatepowersourceisavailable prior to starting the motor driven feed pumps is not specified.
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1202-28, Hydrogen Purge, 11/16/73, Rev. 0 (1) Format indicates that this procedure may belong in 1203
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series, Abnormal Conditions.
(2) Appendices I, II, and IV have not been entered.
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1202-37, Cooldown from Outside the Control Room,11/9/73, Rev. 0
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There does not appear to be any provision for maintaining hot
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standby frcm outside the control room.
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1202-38, Nuclear Services River Water Failure, 8/3/73, Rev. 0
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(1)
Step ?.a does not specify the reduction in plant load that
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(2) Followup action indicates that a cooldown is in progress
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J although it does not appear to be initiated by procedure.
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120.2-28, Hydronen Purge, 11/16/73. Rev. O
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j Step 28.3.9 does not identify sho has the authority to make a
procedural change.
Section 6.2.3 of the Technical Specifications
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does not make provisions for procedural changes where public safety is involved.
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1202-24, Steam Suoply System Ruoture, 6/8/73, Rev. O
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i Step 7 under the immediate manual actions does not appear to
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i provide sufficient guidance for an operator attempting to iso-l late a rupture.
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The precee, ding comm ats are unresolved.
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3.
Industrial Security Program l
The Industrial Security Program was reviewed for implementation.
Target date for full implementation was February 10, 1974.
It was found that the plan was not fully implemented. A revised target
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for impicmentation was identified as prior to fuel loading, with.
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the applicable portion of the program r eportedly being invoked as equipment is installed.
The security program will be the subject of a future inspection.
e 4.
Offsite Review The following procedures were obtained for offsite review by R0:I.
TMI-l Initial Fueling Instruction " Polar Crane" IFI-101.
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b.
Operating Procedure No. 1102-2, Plant Start-up.
c.
Operating Procedure No. 110,'.-4, Power Operation.
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d.
Operating Procedure No.110:'-11, Plant Cooldown.
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e.
Operating Procedure No. 1102-10, Plant Shutdown, f.
Operating Procedure No. 1102-1, Plant Heatup to 525*F.
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5.
Station Orcanization
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The Station Organization Chart, (FSAR Figure 12-1, Amendment 44 dated 11-15-73), filled out with present staff assigrments, was
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provided.
It was noted that resumes in the FSAR are out of date.
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6.
Facility Tour A general tour of the facility was conducted. Main turbine tests were underway and the containment was being readied for leak checks.
l Flood control markings at the River Water Pump Intake facility 'were observed.
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i It was found that facilities have been set up in the chemistry lab
j to provide for operator analysis of boron on back shif ts.
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Examination of SRO candidates was being conducted by the Directorate of Licensing in preparation for fuel loading.
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7.
Facility Procedures Program Connletion
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The licensee has committed to a February 28, 1974 completion date for the Facility Procedures Program, with the following procedures, l
except where indicated, reportedly awaiting final approval.
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a.
Operatine Procedures (1)
1104-28,. Solid Waste Disposal.
(2)
1104-50, Sludge Facility and Industrial Paste
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b.
Administrative Procedures l
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1001, TMI Document Control.
(2)
1006, Procedures for the Conduct of the Retraining Program.
(3)
1004, Site Emergency Plan.
c.
Health Physics Procedures
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(1)
1616, Use of Respiratory Protection Devices.
(2)
1652, Radiation Monitoring System Quarterly Calibration.
(3)
1675, Radioactive Liquid and Gaseous Effluent Release Records and Reporting.
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1709, Plateau Determination, Beckman Wide Beta.
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(5)
1740, Instrument Operation of Hewlett-Packard M. C. A.
(6)
1773, Monthly Source Check.
(7)
1656, Environmental Monitor Calib a. tion.
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(8)
1695, Occurrence of Unsuspected High Radiation.
d.
Corrective Maintenance Procedures
(1)
1401-5.1, CRDM Stator Removal and Replacement.
(2)
1403-1, Nuclear Detector Removal and Replacement.
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Surveillance Test and Calibration Procedures
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(1)
1301-4.5, Secondary Coolant - Weekly.
(2)
1301-6.3, Waste Evaporator Condensate Storage Tank.
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(3)
1301-6.4, Waste Gas Decay Tank.
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1301-9.1, Inservice Tendon Surveillance Program.
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1301-9.6, Condenser Partition Factor.
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1303-1.1, Reactor Coolant System Leakage.
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(7)
1301-4.7, Unit Vent Sampling System.
(8)
1302-5.24, Environmental Monitoring.
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1303-2.1, Main Steam Isolation Valve Move =ent - Weekly.
(10)
1303-4.15, Radiation Monitoring Systems.
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(11)
1303-2.1, Main Steam Isolation Valve Movement - Mont..'v.
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1303-8.2, Ring Girder Inspection Program.
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1300-1, Inservice Inspection.
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1303-5.11, Fire Suppression Air Intake Tunnel.
(15)
1303-11.2, Pressurizer Safety Valves.
(16)
1303-11.3, Main Steam Safety Valves.
.i (17)
1303-11.8, Reactor Building; Local Leakage Rate Test.
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Late Procedures
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E The inspector noted the below problem areas in meeting the
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February 2C Facility Procedures Program ecmpletion date.
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Surveillance Test and Calibration Procedures
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Three surveillance test and calibration procedures are yet to be written, with 13 others lacking review and approval.
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(2)
1:ealth Physics Procedures Eight health physics procedures lack review and approval.
(3)
Preventive Maintenance Procedures
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The p: eventive maintenance to be accomplished has reportedly been identified.
No preventive maintenance procedures have been prepared.
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(4) Administrative Procedures
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Implementing procedures for the Emergency Plan and for the retraining program (Procedure 1006) remain to be completed and approved.
(See Report No. 50-289/73-12, Details, Para-
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graph 3.b) Administrative Procedure 1001, Document Control, (
is reportedly being revised to incorporate the inspector's comments on obsolete procedures and revisions.
(Report No. 50-289/72-18, Details, Paragraphs 2.a(3) and 2.a(4)
refer)
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(5) Alarm Procedures
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l Alarm procedures have been reviewed by PORC but lack final l
approval.
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(6)
Independent Review Of 56 Facility Procedures selected by the General Office
.l Review Board (GORB) for independent review, only 18 have j
been returned with comments and Je remain to be reviewed.
(Report No. 50-289/73-12, Manage =ent Interview, Paragraph C
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refers)
l The licensee stated that Facility Procedures will be completed and approved by February 28, 1974.
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Outstanding Items From Previous Inspections
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a.
Emercency Procedure 1202-4, Reactor Trio i
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The Reactor Trip procedure has been revised to incorporate the inspector's comments contained in Report No. 50-289/73-03,
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Details, Paragraph 6.b.
This item is resolved.
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Control Room Fire Procedure
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Fire in th'e Control Rocm is covered by Appendix A to Emergency Procedure 1202-31, Fire, resolving the inspector's comments in t
Report No. 50-289/73-03, Details, Paragraph 4.k.
c.
Decay Heat and Nuclear Service Water Systems' Procedures The inspector's examination of Procedures 1104-32, Decay Heat
River Water System and 1104-11, Nuclear Service Closed Cooling Water System indicates that the licensee has revised the above procedures to incorporate the comments contained in Report Ne= 50-289/72-05, Details, Paragraphs 5.c and 5.d.
This item L resolved.
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d.
Condensate Storage Tank Diaphraem Surveillance
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The licensee has issued an an. cal surveillance inspection procedure for the diaphrages of the condensate storage tanks (C0T-1A-Al-M and COT-13-Al-M).
(Report No. 50-289/73-06, Paragraph 7 refers.) This item is resolved.
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e.
Reactor Vessel Closure Head Studs (
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The licensee has issued IFP-309, Reactor Vessel Closure Head Studs, specifying methods of protecting the studs from corrosive med-la.
(Report No. 50-289/73-06, Paragraph 8.f refers)
This item is resolved.
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Action Control System
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A formal action control system covering ccamitments contained in i
Met Ed Corporate Office correspondence to the AEC was established on July 3, 1973 by incorporating these items in the PORC action log.
(Report No. 50-289/73-06, Paragraph 11 refers)
This item is resolved.
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j g.
Initial Startup OA Audit Schedule
The inspector verified that a QA audit schedule had been
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established for the initial startup phase of the test program
and was similar to the one in effect for the preoperational
.g test phase.
(Report No. 50-289/73-10, Paragraph G refers)
This
item is resolved.
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h.
Calibration Data Retrieval
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The inspector verified that the licensee could retrieve calibration data in a timely canner.
(Report No. 50-289/73-22, Paragraph 5.a refers) This item is resolved.
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Test Equipment Control Indoctrination The in'spector verified that the licensee has documented that all
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I; of the Met Ed instrument shop personnel had read TI-19, Control j
of Test Equipment.
(Report 50-289/73-22, Paragraph 5.a refers)
This item is resolved.
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Equipment History Cards
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The licensee has reviewed the Equipment History Card records and
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has verified that all the required cards have been received and included in the Met Ed maintenance program.
(Report 50-289/73-23,
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i Paragraph 5.a(6) refers)
This item is resolved.
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Emergency Flood Control Procedure The inspector's examination of Emergency Procedure 1202-32, Flood Control, Revision 02 dated February 1,1974 indicated that R0:I
comments (Report 50-289/73-22, Details, Paragraphs 6.a-e) had
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been fully incorporated in the recent revision with onc exception:
i th; words "for flood control only" were omitted from the statement j
ce vering storage and control of sandbags and pl:stic sheets (6.d).
"ne licensee assured the inspector that these words wculd be j
added. This item is unresolved.
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1.
station Maintenance Ienlementation and Control Procedures
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AdEinistrative Procedure 1016, Implementation and Control of
Station Maintenance has been written and subsequently reviewed by R0:1.
(Report 50-289/73-12, Detalis, Paragraph 3.a refers)
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This item is resolved, m.
Health Physics Procedure 1630 The licensee has revised Health Physics Procedure No. 1630 and incorporated the inspector's comments.
(Report 50-289/73-12,
Details, Paragraph 3.b refers)
This item is resolved.
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i n.
Operator Determination of Boron Concentration j
An Abhormal Procedure 1203-9, Operator Determination of Boron Concentration has been written to provide a simplified procedure
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for operators on the back shift, with separate provisions in the
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l chemistry lab for obtaining the analysis for boron concentration.
J (Report 50-289/73-12, Details, Paragraph 3.c refers)
This item l
1s resolved.
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Refueling Procedure The licensee stated that a refueling procedure will be written
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at least 3 months prior to the first scheduled refueling. While
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the refueling procedure is presently not written, the existing procedural coverage is sufficient to shutdown and defual the i
plant if necessary. The inspector had no further questions on
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this item.
(Report 50-289/73-03, Details, Paragraph 4.n refers)
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9.
Inspection Findines on Compliance with Recuirements of 10 CFR 19
.
The inspector toured the facility, reviewed the contents of bulletin
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boards, and discussed the radiation protection training program with
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the following findings.
a.
Posting
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The bulletin boards located in the entrances to th'e fuel handling areas were examined and the following items were found to be i'
posted.
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(1)
,
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(2) A notice describing documents and where they are available
i for examination as follows.
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(a) Radiation exposure records - Radiation Protection
,
i Supervisor's Office.
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(b) AEC Rules and Regulations - Radiation Protection Supervisor's Office.
(c) Operating Procedures and Technical Specifications -
l Station General Office.
- l (3) AEC Form 3 dated December 1973.
j (4) A map of the Regional Coordination Office for Radiological Assistance and Geographical Areas of Responsibility.
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I The inspector verified that the items in Subparagraph (2)
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preceeding were available for examination, i
b.
Instructions to Workers
,
The licensee reported that personnel involved in the fuel handling
and new employees receive, as a minimum, a four hour basic health
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physics course, a one week intermediate health physics course, and
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, emergency.,' procedure familiarization.
In addition, the personnel involved in' the fuel handling (receipt, inspection, and storage)
,
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have participated in an emergency evacuation drill.
i The inspector had no further questions on tnis item at this time.
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10.
QA Audits - Initial Fuel Receipt, Inscection, and Storage t
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The inspector reviewed six audits conducted by GPU QA during the preparations and receipt, inspection, and storage of initial fuel from December 14, 1973 through February 1,19 74. These audit reports
contained the following information.
a Purpose - A brief statement of areas to be audited.
Details - A detailed discussion of the observations of the auditor.
Findines - A summary of the deficiencies revealed by the audit.
,
Accompanying each audit report is an Audit Report Finding Form, for each deficiency identified, used for obtaining and recording resolu-
,
tion of the item.
This form contain.s the following information.
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Findirt - A brief description of the deCiciency.
(A.
Agreement / Disagreement with Reoorted E ct - Requires signature of person responsible for activity being audited acknowledging the finding.
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Recommended Action - Actions recommended for correction of the deficiency.
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j Group / Activity Responsible - An assignment of the group / activity
responsible to ti.e the necessary corrective action.
}
Resolution - A c' J:ement of the corrective action taken to resolve this deficiency.
i The findings of the auditors included noncompliance with Initial I
Fueling Instructions (IFI) and Procedures (IFP), and apparent viola-tions of Appendix B, 10 CFR 50. The inspector verified the actions
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.
taken by the licensee to correct these deficiencies and had no fur-l ther questions on this item, i
j 11.
Previous Enforcement Items I
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a.
Cleaning and Cleanliness IFI-206
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j In IFI-206 the instruction number, page number, and revision nurbo.r have been entered on the bottem of each page of Ravision 0 I
as required by Section 2 of IFI-201, Document Control.
(R0 l
Inspection Report No. 50-289/73-25, Details, Paragraph 2.a(1)
refers) This item is resolved.
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b. " Document Control IFI-20,1
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Revision 1 to IFI-201, Document Control, was issued on January 8,
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1974. The following requirements were revised.
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(1) Pen and Ink (P&I) change. to IFI's and IFP's may be approved
'
by the Initial Fueling Group (IFG) via telephone conversation
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y with the GPU Shift Engineer.
Changes and exceptions to the
,
instructions and procedures are documented as attachments to an activity summary report to the GPU Site Project Manager from the Lead GPU Shift Engineer, with copies to the IFG.
(R0 Inspection Report No. 50-289/73-25, Details, Paragraphs 2.a(2), 2.a(4) and 2.a(5) refer)
This item is resolved.
.*
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(2)
P&I changes have been specified to be made in ink instead of in pencil. Revision 1 to IFP-501 has been issued as a
,
" clean" copy incorporating the previous changes made in pencil.
(R0 Inspection Report No. 50-289/73-25, Details, Paragraph 2.a(3) refers)
This item is resolved.
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c.
Official Copies
.
Exception 1 to IFI-201 specifies that each page of the IFI's and IFG's will be clearly stamped "Of ficial Copy." This stamp is under the cognizance and control'of the Lead GPU Shift Engineer.
(R0 Inspection Report No. 50-289/73-25, Paragraph 2.a(6) refers)
This item is resolved.
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1 d.
Data Sheets The inspector verified that data sheets have been revised'where
{
required to identify the data recorder or inspector.
(R0 Inspec-
~
tion Report No. 50-289/73-25, Details, Paragraph 2.a(7) ref ers)
i This item is resolved.
12.
Initial Fueling Instructions and Procedures a.
The licensee's implementation of previous commitments to resolve j
deficiencies in IFI-201, IFI-206, IFI-209, IFP-401, IFP-514, and
Generic comments were reviewed. There are no further questions on these items at this time.
(Report No. 50-289/73-25, Details, Paragraph 2.c and Report 50-289/73-20, Details, Paragraph 3 refer)
a
!
i b.
Section 6.11 of Revision 1 to IFP-401 incorporates the requirement
that the Station Superintendent approve any change in sequence of j
source or detector location.
There are no further questions on j
this item at this time.
(R0 Inspection Report No. 50-289/73-20, j
Details, Paragraph 3.b refers)
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l 13. Wes(inghouse W-2 Switches and DB-50 Reactor Trio Breakers
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J a.
The licensee read Wertinghouse Bulletin No. NSD-TB-73-26 and
,
stated that they used four W type switches. These are used in
>
non-safety systems and are located in the 230 kV Substation Building.
The licensee had not seen this bulletin before. The inspector had no further questions for the licensee on this item.
!
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b.
The licensee read Westinghouse Bulletin No. NSD-TB-74-1 and stated that their DB-50 breakers do not have mechanical under-voltage trip devices.
The licensee had seen this bulletin before.
The inspector had no further questions for the licensee on this
.
item.
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14.
Condensate Storage Tank Diaphragm Failure
'
The licensee informed the inspector that the diaphragm. in Condensate Storage Tank COT-1B had failed.
Water in the secondary plant was reportedly replaced in mid-January due to an out-of-specification
-
condition. At that time the Condensate Storage Tank; were drained.
,
During draining, the diaphragm was pulled against sharp areas on the tank's suction screen, rupturing it.
Corrective action proposed by the licensee is to install a device over the suction screen to hold the diaphragm away and instituting an administrative control on draining limits. The diaphragm on Condensate Storage Tank COT-14 will be inspected for similar damage. The licensee stated that he is transmitting a 10 CFR 50.55(c). report on this item.
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