ML19253B725
| ML19253B725 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/28/1974 |
| From: | Mccabe E, Rebelowski T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19253B720 | List: |
| References | |
| 50-289-74-04, 50-289-74-4, NUDOCS 7910180713 | |
| Download: ML19253B725 (6) | |
See also: IR 05000289/1974004
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U.S. ATOMIC ENERGY COMMISSION
DIRECTORATE OF REGULATORY OPERATIONS
REGION I
RO Inspection Report No:
50-289/74-04
Docket No:
50-289
Licensee: p eropolitan Edison Company
License No: CPPR-40
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Three Mile Island Unit 1
Priority:
Category:
B-1
Location:
H ddletown. Pennsvivania
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Typ'e of Licensee:
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jpe of Inspection:
Routine, Unannounced
Dates of Inspection:
Februarv 8. 1974
Dates of Previous Inspection:
Janua
30-31, 1974
Reporting Inspector.:
M U>Uw~ _ mr
28!'IN
T. Rbbelowski, Reactor Inspector
Date
Accompanying Inspectors:
Date
Date
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Other Accompanying Personnel:
Date
Reviewed By:
h. O.
? I2Trf 7Y
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E. C. McCabe, Senior Reactor Inspector, Nuclear
Date
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Support Section, Reactor Operacions Branch
1445
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39101
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SUMMARY OF FINDINGS
Enforcement Action
None
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Licensee Action on Previous 1v Identified Enforcement Items
Not inspected
Unusual Occurrences
None
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O ther Sienificant Findines
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A.
Current
1.
Initial Reactor Building Leak Rate Test
The licensee's approved procedure for the Initial Reactor Building
Leak Rate Test TP 150/3 was issued on February 7, 1974.
(De tails ,
Par,,agraph 2)
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2.
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The licensee is testing penetrations and valves of the containment
isolation systems.
(Details, Paragraph 4)
3.
Schedule of Testing
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The licensee has tentatively scheduled the Structural Integrity
Test and Initial Reactor Building Leak Rate Test during the period
March 4-10, 1974.
B.
Status of Previous 1v Reported Unresolved Items
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1.
Initial Reactor Building Leak Rate Test _
A number of deficiencies identified in the inspector's initial
review of draf t procedure TP 150/3 have been corrected by the
licensee.
(Details, Paragraph 2)
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2.
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The licensee has submitted to the Directorate of Licensing those
items not clearly identified as requiring Type "C"
testing by
10 CFR 50, Appendix J, with additional requirements subsequently
established by Licensing.
(Details, Paragraph 3)
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Management Interview
An cnit interview wr a conduct' . on February 8,1974 at the conclusion of
the inspection.
Items discussed and personnel in attendance follow.
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Licensee Attendees
Mr. J. Barton, Startup and Teat Manager ,
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Mr. R. Toole, Assistant Test Superintendent
Mr. M. Nelson, Technical Engineer
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l.
Initial Reactor Buildir. T ar" Rate Test (ILRT)
The inspector stated that the revised ILRT procedure dated February 7,
1974 resolved a number of deficiencies.
(Details, Paragraph 2)
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2.
10 CFR 50, Appendix J, August 30. 1973
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The licensee stated that five sets of valves were identified to the
Directorate of Licensing for resolution of compliance with 10 CFR 50,
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Appendix J criteria for Type "C"
testing.
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The inspector stated that the Directorate of Licensing's action on
submitted items would be factored into later review of local leak
rate testing.
(Details, Paragraph 3)
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DETAILS
1.
Persons Contacted
General Public Utilities
Mr. J. Barton, Startup and Test Manager
Mr. R. Toole, Assistant Test Superintendent
Mr. M. Nelson, Technical Engineer
2.
Initial Reactor Building Leak Rate Test (ILRT) TP 150/3
The inspector's review of the approved TP 150/3 ILRT, dated February 7,
1974 resolved the following previousl,y identified deficiencies.
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a.
Construction Status Signoffs (Recort 50-289/73-09, Details, 3.b)
)
The revised ILR'i procedure has modified the construction status
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signoffs by the licensee.
b.
Numerical Errors (Report 50-289/73-09, Details, 3.a)
The licensee has corrected numerical errors in the procedure to
conform to the Technical Specifications.
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c.
Revised References (Report 50-289/73-09, Details, 3.c, 3.e)
The licensee has corrected references to include 10 CFR 50,
Appendix J and ANSI 45.4.
d.
Environmental Conditions (Recort 50-289/73-09, Details, 3.d)
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The licensee has modified the procedure to document environmental
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conditions.
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e.
Entrv Into Containment (Report 50-289/73-09, Details, 3.f)
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The licensee has indicated that those members of the ILRT
inspection teams who enter the pressurized containment will
be physically adaptable to its elevated pressures.
The licensee
stated that his' review of local laws pertaining to entry into
areas under pressure has been made, with those rules not appli-
cable to pressures under 14 psig.
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f.
Inspection of Containment (Recort 50-289/73-09, Details, 4.a)
The licensee has sequenced the Structural Integrity Test (SIT)
prior to the ILRT.
The requirements for a survey of accessible
interior and exterior surfaces of containment structures and com-
ponents are planned to be completed as a prerequisite for the SIT.
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g.
Component Venting (Recort 50-289/73-09, Details, 3.h)
The licensee has identified the components that require venting
or removal from containment in Paragraph 7.6 of the revised
procedure.
h.
References (Recort 50-289/73-09, Details, 3.1)
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References to the FSAR have been corrected in the procedure to
reflect the latest changes.
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i. Valve Closure (Recort 50-289/73-09, Details, 4.a. (2))
The licensee has revised the procedure to require normal closure
of containment isolat' ion valves withcut preliminary exercising.
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Additional ILRT Procedure Changes (Recort 50-289/73-09, Details, 4.b)
The licensee has revised or identified the action to resolve the
following.
(1) Holding time at pressure plateaus for a minimum ttme of 36
hours is addressed in the revised procedure.
(2) The licensee has determined that the core flood tank can
withstand an external pressure of 30 psig.
(3) The licensee has established a temperature stabilization
criterion of l'F/hr during the ILRT.
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(4) The licensee has established criteria for partial loss of
test instrumentation during the ILRT.
Items a. through j. preceeding were reviewed by the inspector who had
no further questions in these areas.
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3.
10 CFR 50, Aooendix J (Recort 50-289/73-09, Details 2)
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The licensee's review of plant design for compliance with Appendix J
identified five sets of valves where the method or requirements for
1 4 4 5 1 i. ,S ,)
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Type C testing was undetermined. The Directorate of Licensing, after
evaluation of the licensee's review, has established the following.
The licensee has been directed to add an automatic isolation
a.
valve at the location of present check valve RB-V2 on RB normal
cooling coils.
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Directorate of Licensing review of the licensee's method of testing
b.
the Reactor Building purge valve by the application of pressure
between isolation valves identified no deficiencies.
Additional system valves on RB emergency cooling coils, RB main
c.
recirculating fan motor coolers, and the decay heat removal sys-
tem are required to be tested by "A" type containment tests.
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The inspector had no further question's on these items at this time.
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4.
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The licensee is presently testing the Reactor Building isolation
valves to procedure TP 151/1.
Approximately fifty additional isolation valves are to be tested
prior to the Structural Integrity Test.
The inspector witnessed
one tes't of isolation valve BSV30B.
Excessive leakage was noted
and repairs were to be instituted by the licensee prior to retesting.
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The calibration curves for the test rotameters were reviewed with
no deficiencies identified.
The inspector stated that review of licensee's procedure TP 151/1
would be conducted prior to the ILRT test.
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