IR 05000317/1978030
| ML20062G491 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs |
| Issue date: | 11/09/1978 |
| From: | Dante Johnson, Keimig R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20062G488 | List: |
| References | |
| 50-317-78-30, 50-318-78-27[, NUDOCS 7812290034 | |
| Download: ML20062G491 (6) | |
Text
-
. -
- -. -
__
-
_ =.
-
.
.
.
'
U.S. NUCLEAR REGULATORY COMISSION
-
OFFICE OF INSPECTION AND ENFORCEMENT 50-317/78-30 Report No.
50-318/78-27 50-317 Docket No.
50-318 UPK-5')
C License No. DPR-63 Priority Category C
--
Licensee:
Baltimore Gas and Electric Company P. O. Box 1475 i
l Baltimore, Maryland 21203 Facility Name:
Calvut Cliffs Nuclear Power Plant, Units 1 and 2 Inspection at:
Lusby, Maryland spection conducted:
October 23-26, 1978 Inspectors:
[]
/dbm
[
//
h,#
&
D. F. Johnson, Repor lifspecto date signed date signed date signed Approved by:
/5
'OV'
ff
//!f[7?
c R.R.Keimig,/phief,Keactorpy6jens date signed Section No.V1, RO&NS Brancl/
spection Summary:
Inspection on October 23-26, 1978 (Combined Report Nos. 50-317/78-30 and 50-318/78-27)
Areas Inspected:
Routine, unannounced inspection by a regional based inspector of plant operations including shift logs and records; licensee followup actions
'
concerning previous inspection findings; and post refueling startup activities
'
of Unit 2.
The inspection involved 10 inspector-hours on site for Unit 1 and 18 inspector-hours on site for Unit 2 by one NRC inspector.
Results: No items of noncompliance were identified.
I 7812290037
.
i Region I Fonn 12 (Rev. April 77)
,
,,
- - ~ _ -._---
-
, _-,. --_..,
,7-
-.c,
-
,, _. - - -. -
.
.
,
.
DETAILS 1.
Persons Contacted Mr. R. Douglass, Chief Engineer Mr. C. Dunkerly, Shift Supervisor Mr. J. Hill, Shift Supervisor
- Mr. J. Lemons, Nuclear Plant Engineer - Maintenance
- Mr. J. Lippold, Nuclear Engineer Mr. M. Miernicki, Performance Engineer Mr. J. Mihalcik, Fuel Management Enginee:-
- Mr. L. Russell, Nuclear Plant Engineer - Operations Mr. J. Steelman, Fuel Management Engineer Mr. T. Sydnor, Performance Engineer Mr. J. Watson, Shift Supervisor The inspector also interviewed several other licensee employees during the inspection. They included reactor operators, plant operators, technicians, and general office personnel.
- denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (317/78-25-01):
Failure to provide test data for air lock leak tests dated October 6,1976, October 14, 1975, April 1975, and October 1974.
The inspector verified by review of the completed test data sheets for the above dates that the required tests were performed.
(Closed) Unresolved Item (317/78-25-12, 318/78-19-12):
Procedure M-171-1, " Personnel Air Lock Seal Test," Revision 1, September 13, 1978, has been revised to require a test pressure of 15 + 6 psig and the recording of barometric pressure.
The inspector verified by review of completed test data performed on September 20, 1978, that the test procedure and test results are in conformance with Technical Specification requirements.
(Closed) Unresolved Item (317/75-25-03):
The inspector verified by review of a supplementary report for the Reactor Containment Building Integrated Leakage Rate Test dated October 16,1978, that the information supplied met the requirements of 10 CFR 50, Appendix J, Section V.B.3 and that the incorrect data previously reported were correcte.
-
.
t
(0 pen) Unresolved Item (318/78-25-05):
Unidentified source of oil present on the floor in #21 diesel generator room.
The licensee investigated the cause and determined it to be a lubri-cating oil leak from the diesel erigine.
It appeared to be coming from the timing chain housing cover. A maintenence request (MR-78-24961) was issued on October 25, 1978, to effect repairs. This item remains unresolved pending action by the licensee.
3.
Post Refueling Plant Operations (Unit 2)
The inspector reviewed facility records and operating and a.
surveillance procedures on a sampling basis to determine whether systems disturbed during the refueling outage were returned to service in accordance with approved procedures, and that sur-veillance tests were performed during the refueling outage as required by the Technical Specifications.
The following pro-cedures were reviewed:
OP-6, Pre-Startup Checkoff, Revision 9, May 10,1978
--
(completed through mode 3, October 24,1978).
OP-1, Plant Startup from Cold Shutdown to Hot Shutdown,
--
Revision 10, September 13, 1978.
0P-2, Plant Startup from Hot Standy to Power Operation,
--
Revision 5 February 24, 1977.
Technical Support Test Procedure TSP-22, Reactor Coolant
--
System Pressure Test, Original, October 18, 1978.
Test completed October 24, 1978.
STP-0-5-2, Auxiliary Feedwater System, Revision 5, March
--
15, 1978. Test completed October 25, 1978.
STP-0-86-2, Boration Flow Path Temperature Determination,
--
Original, July 26, 1978.
Test completed October 20, 1978.
STP-0-44-2, Containment Sump - Suction Screen Inspection,
--
Original, July 27, 1976.
Test completed October 21, 1978.
STP-0-82-2, Hose Station Inspection - Shutdown, Original,
--
March 17, 1978.
Test completed October 21, 1978.
!
!
,
..
.
.
'
.
STP-0-56-2 ESFAS Equipment Response Time Test, Original,
-
,
--
August 6, 1976.
Test completed October 20, 1978.
STP-0-73-2, Engineered Safety Features Equipment Perform-
--
ance Test, Revision 3, March 15,1978.
Test completed October 14, 1978.
STP-0-66-2, Quarterly Valve Oper:Lility Verification -
--
Shutdown, Revision 5, November 3, 1977.
Test completed September 20, 1978.
b.
The inspector verified by direct observation that the follow-ing activities were conducted in accordance with approved procedures and within Technical Specification limits.
Plant heatup to hot standby.
--
Initial approach to criticality including shutdown margin
--
calculations, rod drop times, rod withdrawal sequences, 1/M plots, estimated critical boron ccncentration, and nuclear instrumentation operability and calibration.
.
Criticality.
--
Shift manning.
--
The inspector reviewed and observed the performance of Post c.
Startup Test Procedure 78-1, " Unit 2 Second Cycle Initial
~
Approach to Criticality and Low Power Physics Testing,"
Revision 0, October 20, 1978.
No items of noncompliance were identified.
4.
Review of Plant Operations (Units 1 and 2)
The inspector reviewed the following logs and records:
.
Auxiliary Building Log Sheets for the period August 1,1978,
-
--
'
through August 31, 1978.
Turbine Building Log Sheets for the period August 1,1978,
'
--
through August 31, 1978.
l l
~
\\
'
<
I 's
.
.
.
Outside Log Sheets for the period August 1,1978, through
--
August 31, 1978.
Service Building Log Sheets for the period August 1,1978,
--
through August 31, 1978.
Nuclear Plant Engineer - Notes and Instructions for the
--
period August 9, 1977, through October 21, 1978.
Nuclear Plant Engineer - Standing Instructions - last entry
--
made February 2, 1977.
Shift Supervisor's Log for the period September 25, 1978,
--
through October 23, 1978.
Lifted Wire and Temporary Jumper Log - Unit 2 - entries from
--
'
June 9, 1975, through October 23, 1978.
Unit 1 - entries from October 8,1975, through September 14, 1978.
The inspector observed that an audit was performed pursuant to CCI-117 requirements on October 22, 1978, for Unit 2 and on September
-
12, 1978, for Unit 1.
The logs and records were reviewed to verify the following items:
Log keeping practices and log book reviews are conducted in
--
accordance with established administrative controls.
Log entries ~ involving abnormal conditions are sufficiently
--
detailed.
.
-
Operating orders do not conflict with Technical Specification
--
requirements.
Problem identification reports confirm compliance with Tech-
--
nical Specification repurting and Limiting Conditions for Operation.
Log book reviews are being conducted by the staff.
--
Jumper log and tagging log entries do not conflict with
--
...
Technical Specification requirements.
.
,
N e N.
s.
4. - -
_
_ - -.
.
O
.
.
Jumper, lifted lead, and tagging operations are cariducted in
--
conformance with established administrative controls.
Acceptance criteria for the above review included inspector judge-ment, requirements of applicable Technical Specifications and the following administrative control procedures.
CCI-106, "Special Orders by the Chief Engineer," Original,
--
April 24,1972.
CCI-142, " Safety and Safety Tagging," Change 3, October 14,
--
1976.
CCI-114, " Plant Logs," Change 8, January 2,1978.
--
CCI-117, " Lifted Wire and Temporary Jumper Logs," Change 1.
--
July 27,1976.
No items of noncompliance were identified.
5.
Exit Interview The inspector met with licensee representatives (denoted in Para-g.aph 1) at the conclusion of the inspection on October 26, 1978.
The inspector summarized the purpose and scope of the inspection and the findings presented in the details of this report.
~
i