IR 05000320/1977039
| ML19220A544 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/04/1977 |
| From: | Caphton D, Higgins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220A538 | List: |
| References | |
| 50-320-77-39, NUDOCS 7904230056 | |
| Download: ML19220A544 (4) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
..
..
Region I Report No.
77-39 Docket No.
50-320 License No.
CPPR-66 Priority
-
Category B(1)
Licensee:
l'etropolitan Edison Cctrpany P.O. Box 542 Readirg, Pennsylvania 19603 Facility Name:
Three Mile Island Nuclear Station, Unit 2 Inspection at:
Middletown, Pennsylvania
.
Inspection conducted:
September 21 and 22. 1977 Inspectors:
___
/o[][77
[.'C.H s, Reactor Inspector date signed date signed date signed Approved by:
C'I S.-
ro/u/77
%
D. L. CaphEon, Chief, Nuclear Support Section
/da'te signed
_
No. 1, RO&NS Branch Insoection Summary:
~
Inspection on September 21 and 22,1977 (Recort No. 50-320/77-39)
Areas Inspected:
Routine, unannounced inspection of containment leak rate testing. The inspection involved 20 inspector hours onsite by one NRC inspector.
Results: No items of noncompliance were identified.
- Region I Fom 12 UE
.D
-
I (Rev. April 77)
790423o0 5(,
, -.
DETAILS _
Persons Contacted l.
The below technical and supervisory level personnel were contac Mr. T. Hawkins, Assistant Test Superintendent Mr. T. Mackey, Engineer, Nuclear
- Mr. M. Nelson, Technical Engineer Mr. L. Schroeder, Test Engineer
- Mr. R. Toole, Test Superintendent
- denotes those present at exit interview.
Licensee Action on Previous Insoection Findinas 2.
Based on a review of Rev. O of (0 pen) Open item (320/77-26-20):15,1977,14 of the 15 issues under this TP 150/3 dated September The procedure, h6 wever, does not address the correction of RTD readings to their calibration curves as required item are closed.
This item is unresolved.
by Section III.A.3.(c) of Appendix J.
Based on a review of Rev. O of (Closed) Open item (320/77-26-21):
TP 150/2, the six issues under this item are closed.
i The inspector discussed Unresolved item (320/77-26-24):
This item re-(0 pen)
proposed administrative controls with the licensee.
mains unresolve f pending formalization of the proposed controls.
Local Leak Rate Test Witncssing 3.
The inspector witnessed local leak rate tests (LLRTs) performed o valves MS-V-72, 81, 99 and 100 in accordance with TP 151/1, T With the exception of the below items, the inspector had no furthe
_
questions on the LLRTs.
Flowmeter Calibration Curves _
a.
The licensee appeared to be using generic calibration curves for the LLRT flonneters vice specific curves for each review of onsite laboratory calibration records and ficwmeter vidual flowmeter.
calibration check infomation and is designated Iten No.
(320/77-39-01).
,
L
.
I
_
i G5'259
~
.
.
..
b.
Procedural Items These items are collectively de'.gnated Unresolved item No.
(320/77-39-02) pending revision of the procedure.
(1) Method A When Method A is selected for quantifying upstream bound-ary valve leakage, inaccurate results could be obtained if the two readings are not taken under identical condi-tions.
(2) Method B This method is non-conservative unless the difference be-tween the upstream flowmeter and downstream flowmeter ob-tained in the first step is added to the CIV leakage ob-tained in the second step.
(3) Stabilization Inaccurate and possibly non-conservative results could be obtained if readings are taken prior to achieving pressure and flow stabilization.
4.
Nuclear Service River Water System (NSRWS)
The containment isolation valves (CIV's) in the NSRW System appear to meet the testing criteria for Type C testing in Appendix J.
Additionally, this system will be in operation during the Integrated Leak Rate Test (ILRT) which implies that these valves must be Type C tested under Section III.A.l(d) of Appendix J and the results added to the ILRT results.
The Final Safety Analysis Report, how-ever, states that these valves will not be Type C tested.
>
This item will be referred to NRC management for further review.
(Item i
No. 320/77-39-03)
>
5.
Containment Intecrated Leak Rate Test (CILRT)
The inspector reviewed TP 150/3, Rev. O dated September 15, 1977
" Reactor Building Initial Leak Rate Test".
the following two items are unresolved (Item No. Based on this review, 320/77-39-04).
!
i
.
i G5'260
.
-
..
.
a.
Acceptance Criteria In order to meet the acceptance criteria of Section III.A.4(b)
of Appendix J the leakage rate at the 95% upper confidence level must be less than 0.75La.
b.
Calibration Check The procedure did not specify a calibration check of the
'
humidity instruments with an NBS traceable psychrcmeter as required by ANSI N45.4 and ASTM E337-62.
6.
Unresolved Items Items about which more information is required to determine accept-ability are considered unresolved.
Paragraphs 2, 3.a. 3.b and 5 of this report contain unresolved items.
.
7.
Exit Interview At the inspection's end the inspector held a meeting (See Detail 1 for attendees) to discuss the inspection scope and findings. The unresolved items were identified.
,
e
.
=
t lib 261