ML20054K907
| ML20054K907 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 06/15/1982 |
| From: | Bettenhausen L, Nicholas H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20054K899 | List: |
| References | |
| 50-322-82-11, NUDOCS 8207060271 | |
| Download: ML20054K907 (15) | |
See also: IR 05000322/1982011
Text
..
,
_ _ _ _ _
7
i ;;
.
'
'
.
.
~
_
,
K.
\\
.
s.
'
U.S. NUCLEAR REGULATORY COMMISSION
,
REGION I
Report No.
50-322/82-11
Docket No.
50-322
License No. CPPR-95
Priority
- -
Category
B
Licensee:
Long Island Lighting Company
175 East Old Country Road
Hicksville, New York 11801
Facility Name:
Shoreham Nuclear Power Station
Inspection at:
Shoreham, New iork
Inspection conducted: May 11-14, 17-20, 1982
Inspector: N.k.
/[ 8h
m
H. H. Nicholas, Reactor Inspector
/ date/ signed
dqte signed
~~
date signed
..,
6//S/61
Approved by:
Jew
L. H. Bettenhausen, Chief, Test. Program ^
cate signed
~
s
'
Section
- .
,
1
'
e
-
Inspec tion Summary:
,c
-
,
.
~
,\\
_
s_
_
Inspectinn on May 11-14, 17-20, li8f (Report No. 50-322/82-11)[
-
,
Areas Inspected:
Routine unannounced inspection of licensee's action on. previous
'
"
inspection findings; part 21 report followup; preoperational testuprogranP status
-
'
including test program implementation, test procedure review,, procedure verifica-
~
~
~-
tion, test witnessing, test results evaluation and operations quality'nsurance
procedure audits; and tours of the facility. The inspection involved 72 inspector -
'
hours on site by one NRC region - based - inspector.
.
f'
.
_
Results: One violation was identified (Failure to conduct surveillanse tests of
~
^
,
battery systems).
-
,
.
-
~.
_, .
8207060271 820618
-
--
PDR ADOCK 05000322
%
-
>
%
G
PDR ,
a
"
-
+ , -
-
u-
Q
s
.
-
.
.
.
S
-
,
,
f
-
DETAILS
4
1.
Persons Contacted'
Long Island Lighting Company
R. Gutman, Maintenarce Engineer
- s
J. Kaczor, Assistant Project Engineer
J. Kelly, Manager, Field Quality Assurance
,
W. Klein, Leaa Startup Engineer
-
,
+*
A. Muller, Quality Control Engineer
4
J. Rivello, Plant Manager
.
+
D. Terry, Assistant Startup Manager
+*
R. Werner, Operating Quality' Assurance Engineer
E. Youngling, Startup Manager
,
Stone and Webster Engineering Corporation
W. Matejek, Lead Advisory Engineer
+
T. Paulantonio, Lead Startup Engineer
,
General Electric Company
-
K. Nicholas, Lead Startup Engineer
'
J. Reilly, Operations Manager
U.S. Nuclear Regulatory Commission
,
+*
J. Higgins, Senior Resident Inspector
'
!
denotes'those present at exit interview on May 14,.1982.
+
denotes those present at exit interview on May 20, 1982.
2.
Licensee Action on Previous Inspection Findings
(Closed) Inspector Followup Item (50-322/81-03-01) Procedure PT 123.001,
Standby Liquid Control (SBLC) System, was written on June 21, 1977.
~.
.The most recent General Electric design-specification for the SBLC
system is document no. 22A1482AJ, revision 3, issued January 17, 1980,
s+
4
4
,
$
-
,
..,.._.r.
., --.- - _ . -
~
. ,
, - ,
_
. - -
- -
.
.
Long Island Lighting Company
2
P
i
The inspector noted that the amount of sodium pentaborate called for in
the test procedure and the acceptance criteria differed from the amount
specified in the G.E. design document.
The inspector reviewed G.E. Specification 22A1482AJ, Revision 3,
Figure 1, for SBLC Storage Tank Sodium Pentaborate volume and concen-
tratic,n limits, and procedure PT 123.001-1, Approved September 4, 1981.
The inspector verified that the test procedure acceptance criteria
reflects current design specifications.
This item is closed.
(Closed) Inspector Followup Item (50-322/81-03-02) In reviewing proce-
dure PT 119.001, Reactor Core Isolation Cooling (RCIC) System, the
inspector expressed concern that acceptance criteria in the procedure
were marked "later, to be provided at a future date", and that the
method used to calculate the net positive suction head is not provided
in the test procedure.
The inspector reviewed PT 119.001-1, Approved April 12, 1981. The
inspector verified that required acceptance criteria are included and
reflect the current design specifications. The inspector verified the
addition to the test procedure of RCIC pump minimum NPSH calculations
for condensate storage tank to vessel and suppression pool to vessel,
in addition to calculations to determine RCIC pump head versus speed.
This item is closed.
(Closed) Unresolved (50-322/82-04-02) None of the three Emergency
Diesel Generator crankcase vents extending from EDG rooms had bird
screens installed on them, as is indicated on flow diagram FM 44A-10.
The inspector verified the installation of bird screens on all three
EDG crankcase vent pipes. This item is closed.
3.
Part 21 Report Followup
3.1 General
In a letter to the Director, Office of Inspection and Enforcement,
U.S. Nuclear Regulatory Commission, dated March 19, 1982, and in
accordance with Title 10, Chapter 1, Code of Federal Regulations,
Part 21, Transamerica Delaval Incorporated, notified NRC of a
potential defect in a component of Standby Diesel Generators. A
potential problem exists with the sensing line between the starting
air storage tank and the starting air compressor. Air tanks are
seismic category 1.
The starting air compressor is not seismically
supported.
The sensing line is not supplied by Transamerica
Delaval. On some installations, Transamerica Delaval furnished a
,
I
seismically qualified manual isolation valve for the sensing
i
line. On installations where the isolation valve was not supplied
by Transamerica Delaval, it is not known if the valve is seismically
,
l
qualified, or if a valve was installed. During a seismic event,
j
the sensing line could fail, causing the starting air pressure to
j
bleed down to a point where the engines would not start if required.
.
w
--
--
,
a
.- -
c-
.
.
.
Long Island Lighting Company
3
3.2 Scope
The inspector discussed this with the cognizant engineer and-
other licensee representatives reviewed the system description
and Diesel Generator Air Start flow diagram FM-448-4; and visually
inspected all three Diesel Generator Air Start Piping Systems.
3.3 Findings
The following observations and determinations were made:
In each system the starting air compressor, the air dryer
--
.
and associated piping and and sensing line up to the four
!
inch header pipe are non-seismic.
--
The four inch header, the four inch check valve, the piping.
and the starting air storage tank, are seismically mounted
and seismically supported.
--
The starting air storage tank and the four inch check valve
are seismic category 1.
--
The air pressure sensing line does not connect between the
starting air storage tank and the starting air compressor,
but rather, connects from the starting air compressor to
the four inch piping header. This connection point of the
sensing line is between the four inch check valve and
the starting air compressor.
--
The inspector verified that the four inch check valve was
tested for reverse flow and leakage from the starting air
storage tank back to and through the compressor to atmos-
phere. This was accomplished successfully during preopera-
tional testing of the DG air start system.
The starting air
storage tank fully charged, the compressor was secured and
a section of pipe opened to atmosphere between the four inch
check valve and the starting air compressor.
The inspector verified that this potential deficiency is not
--
a problem at the Shoreham Station. The inspector had no
further questions.
.
4.
Preoperational Test Program
4.1 References:
SNPS Final Safety Analysis Report
--
--
SNPS Safety Evaluation Report, NUREG-0420, and Supplement 1
--
SNPS Startup Manual
--
Stone and Webster, Construction Site Instructions, House-
keeping
SNPS Project Schedules, Startup Disciplines
--
-
_.
.
.
Long Island Lighting Company
4
--
SNPS Startup Monthly Report
--
IEEE 308-1974, Class 1E Power Systems for Nuclear Power
' Generating Stations
--
IEEE 387-1972, Diesel Generator Units Applied as Standby
Power Supplies for Nuclear Pcwer Generating Stations
--
IEEE 450-1975, Maintenance, Testing, Replacement of Large
Lead Storage Batteries for Generating Stations and Substa-
tions
RG 1.9-1971, Selection of Diesel Generator Set Capacity for
--
Standty Powe* Stpplies
--
RG 1.32-1977, Safety Related Electric Power Systems for
Nuclear Power Plants
RG 1.41-1973, Preop Testing of Redundar,t On Site Electric
--
Power Systems to Verify Proper Load Group Assignments
--
RG 1.68-1977, Initial Test Programs for Water Cooled Reactor
Power Plants
RG 1.93-1974, Availability of Electric Power Sources
--
--
RG 1.108-1977, Periodic Testing of Diesel Generator Units
Used as On Site Electric Power Systems
--
RG 1.118-1976, Periodic Testing of Electric Power and
Protection Systems
--
RG 1.128-1978, Installation, Design of Large Lead Storage
Batteries for Nuclear Power Plants
RG 1.129-1977, Maintenance, Testing, Replacement of Large
--
Lead Storage Batteries for Nuclear Power Plants
4.2 Test Program Status and Implementation
The inspector met with the Startup Group and other licensee
representatives and discussed the status of construction; system
turnovers; completed preoperational tests and remaining tests;
test procedures approved for testing, awaiting results evaluation,
and awaiting review and approval; tests for which results have
been evaluated and approved; and completed systems turned over to
plant staff. The discussions included the interface between the
preoperational test program and the startup test program. The
inspector reviewed the monthly startup report, the project
schedule startup charts for all disciplines, a test matrix status
of tests and. test procedures, and plans of the day showing work
in progress and tests of components and systems scheduled to
start or being tested.
As a result of these discussions and review of documents relative
to test program status and implementation, no discrepancies were
noted.
The inspector had no further questions.
4.3 Test Procedure Review, Verification and Test Witnessing
4.3.1
Test Procedure Review and Verification
The procedures listed below were reviewed in preparation for test
witnessing. They were reviewed for technical and administrative
1
.
Long Island Lighting Company
5
adequacy and for verification that adequate testing is planned to
satisfy regulatory guidance and licensee commitments.
J
--
PT 425.001, Approved April 20, 1981, Primary Containment Inerting
System
l
--
PT 119.001-1, Approved April 12, 1981, Reactor Core Isolation
'
-
Cooling System'
.
--
PT 202.001-1, Approved March 12, 1982, High Pressure Coolant
Injection System
--
PT 307.0018-1, Approved February 19, 1982, Emergency Diesel
Generator 102 - Mechanical
--
PT 307.0038, Approved May 27, 1981 Emergency Diesel Generator
102 - Electrical
The procedures were reviewed for manual review and approval,
procedure format, test objectives, prerequisites, environmental
conditions, references, initial conditions, test objectives are
met, performance verification, recording conduct of test, restora-
tion of system to normal after test, identification of personnel
conducting and evaluating test data, and independent verification
of initial steps or parameters.
Tne inspector ascertained that
the procedures are consistent with regulatory requirements,
guidance and licensee commitments.
Discussions were held with
the cognizant engineers in preparation for testing of these
systems.
Concerns of the inspector were addressed. The inspector
had no further cuestions.
4.3.2 Test Witnessing
Test witnessing by the inspector included the following:
Observations of overall crew performance which included:
.
Approved procedure with latest revision available and in
--
used by test personnel;
--
A designated person in charge and conducting the test;
--
Minimum test personnel requirements met;
Qualified personnel performing the test;
--
--
Test precautions followed and prerequisites met;
--
QA/QC hold and witness requirements met;
Proper plant supporting systems in service;
--
Special test and measuring equipment required by the test
--
j
procedure calibrated and in use;
.
Procedure is technically adequate for the test;
--
l
--
Testing performed as required by the test;
Test personnel actions appeared to be correct and timely
'
--
during performance of the test;
<
,
-
-_
s
--
,
,
- * - -
- - , .
.
.
Long Island Lighting Company
6
Test results appear to be acceptable;
--
--
All data is collected and properly documented for final
analysis; and,
--
Criteria for interruption and continuation of testing is
adhered to.
Observations independent measurements and calculations and review of
documentation of test results by the inspector indicated that acceptance
criteria has been met.
4.3.2.1
High Pressure Coolant Injection System (HPCI)
The preoperational test of the HPCI system should demonstrate
the capability of the HPCI system to inject coolant into the
reactor vessel automatically a..d reliably in the event of a
loss of coolant accident.
The test is conducted in three
stages:
individual component testing; uncoupled turbine
testing; and coupled turbine testing.
The HPCI system logic tests consist of vacuum breaker isolation
logic, isolation and trip logic, auto initiation logic, and
miscellaneous logic. Portions of the logic testing and
valve lineups were witnessed by the inspector.
The inspector witnessed the following portions of the HPCI
system uncoupled turbine testing:
idle speed, remote manual trip, local manual trip, vibration readings, stability of
turbine control system by increasing speed to low speed for
safe operation (2100 RPM) and then to high speed (4000 RPM),
mechanical overspeed trip, and time lapse and turbine speed
for the automatic stop valve reset.
The inspector made independent measurements and calculations.
The observed results indicated that acceptance criteria had
been met.
No discrepancies were noted. The inspector had no questions
on these portions of HPCI testing.
4.3.2.2
Emergency Diesel Generator - 102 (EDG)
The preoperational test of EDG - 102 should verify correct
operation during its starting, loading, and shutdown.
The inspector witnessed portions of the EDG - 102 electrical
test which included initial manual start, testing of diesel
control switches, testing auto start and phase rotation, and
testing synchronous operation and two hour rated load capability.
No discrepancies were noted. The inspector had no questions
on this portion of the emergency diesel generator testing.
.
.
Long Island Lighting Company
7
4.3.2.2.1
EDG Supporting System
The EDG Service Water System is one of several systems-
needed for supporting EDG operation. As documented in
Inspection Report 50-322/82-04, in section 4.3.2.1, "EDG
Service Water System", the inspector observed salt encrus-
tation on flanges and top and bottom caps of reliet valves
P41-ROV-019A, 019B and 019C. These valves are installed on
the bypass line of the service water outlet from the diesel
engine ccolers.
This condition is indicative of possible
internal salt encrustation which could make these valves
inoperable. The inspector examined the relief valves and
verified that all three valves were removed, cleaned,
adjusted, tested and reinstalled. The inspector was satis-
fied with this corrective action and had no further questions
on this iten.
4.4 Test Results Evaluation
4.4.1
Procedures Reviewed
The preoperational test procedures and acceptance test procedures
listed in Attachment A were reviewed to ascertain whether uniform
criteria are being applied for evaluating completed preoperational
tests to assure their technical and administrative adequacy.
The inspector reviewed the test results and verification of licensee
evaluation of test results by review of test changes,-test exceptions,
test deficiencies, "As-Run" copy of test procedure, QC inspection
records, and verifying that the test results have been approved.
4.4.2
Findings:
The following unresolved test exceptions were noted in this review:
Procedure
Title
Exceptions
PT 102.001-1
Circ Water
003, 007.
PT 123.001-1
SBLC
017, 018, 019, 020, 021.
PT 501.002
RSDP Halon
002, 003.
PT 622.001
LpMS
002, 004, 006.
AT 301.001
138 KV
002, 003, 004.
AT 670.003
120 VAC UPS INV
001, 002.
These procedures will be examined on subsequent inspections for
resolution of the listed exceptions and approval by the licensee.
This is an inspector followup item (50-322/82-11-01).
In reviewing the completed test procedures for test results evalua-
tion and procedure verification, the inspector observed the following:
,.
-
- - _____
.
.
Long Island Lighting Company
8
SNPS Startup Manual, section 8.4.2 X1, Exceptions Sheet,
states, in part, "In this section note any deviation from the
indicated tests and explain how the deviation does not invalidate
the other sections of this test."
In reviewing these procedures
the inspector noted that some items in the exception column are
annotated and signed off in the disposition column by refe n ce
to an Engineering and Design Change Request (E&DCR) which nad
been written for the item.
In reviewing these completed test
packages, it was not apparent to the inspector whether the excep-
tion had been completed and cleared. This can lead the reviewer
to believe that the exception is resolved when in fact it is
still open.
Because this completed test package is the official plant document
describing the test and the system performar.ce that is reviewed
by engineering, station staff, and the NRC for the evaluation of
test results, the inspector identified no simple method to allow
.'
the reviewers or the inspector to verify the closing of these
exceptions.
The licensee representative acknowledged the inspector's concern
and stated that even though the exceptions are tracked by means of
the master punch list and E&OCR's, amplifications would be forth-
coming for the Startup Manual and the completed test packages, to
document resolved exceptions. This will be examined on a subse-
quent inspection and is an unresolved item (50-322/82-11-02).
In review of the test procedure approval dates, test results
evaluation review approval dates, and the test dates for the
Performance Tests and Service Tests of the batteries, the inspector
noted the following:
--
The 24 VDC battery A was performance tested and service
tested through the period January 14, 1980 to February 15, 1980.
Test results were evaluated and approved on August 26, 1980.
--
The 24 VDC battery B was performance tested and service
tested through the period January 17, 1980 to February 25, 1980.
Test results were evaluated and approved on September 17, 1980.
--
The 125 VDC battery A was performance tested and service
tested through the period July 30, 1980 to September 9, 1980.
Test results were evaluated and approved on October 22, 1980.
10 CFR 50, Appendix B, Criterion AI, requires a test program with
written test procedures to demonstrate that systems and components
will perform satisfactorily in service, incorporating the require-
ments and acceptance limits contained in applicable documents.
10 CFR 50, Appendix A, Criterion 18, requires that electrical power
systems important to safety, shall be designed to be tested periodi-
cally for operability and functional performance.
-_
- - - - - _ - _ _
_-
.
.
Long Island Lighting Company
9
Shoreham FSAR Section 8.3.2, DC Power Systems, describes a periodic
test program which includes battery capacity tests. These tests
meet the intent of IEEE 308-1971 to determine battery capacity.
The performance discharge test, as listed in IEEE 308-1971, will
be performed according to IEEE 450-1972.
"Also, a battery service
test as described in IEEE 450-1972 will be performed during
refueling outage or at some other outage with intervals between
tests not to exceed eighteen months." (FSAR p8-3.44).
Contrary to the above, as of May 20, 1982, battery service testing
has not been conducted an the following three batteries within
the prescribed eighteen mcnths:
--
The 24 VDC battery A, due to be tested by August of 1981.
--
The 24 VDC battery B, due to be tested by August of 1981.
--
The 125 VDC battery A, due to be tested by March of 1982.
This item is a violation (50-322/82-11-03).
4.5 Operations Quality Assurance (0QA) Procedure Audits
The Shoreham 0QA audit group conducts an unscheduled verification
activity audit of completed preoperational test procedure packages.
The audit addresses the requirements of the FSAR, SER, Startup
Manual, OQA Manual, Regulatory Guides and test procedures.
The inspector selected, at random, the following sample of completed
preoperational test procedure packages that were audited by 0QA
group:
--
PT 117.001-3, Instrument and Service Air
Audit Report No. 80-11, Audited March 4-7, 1980.
Audit Review approved March 10, 1980.
--
PT 709.001, Reactor Water Cleanup
Audit Report No. 82-22, Audited April 22-30, 1982.
Audit Review approved May 11, 1982.
--
PT 136.004, Jet Pump Instrumentation
Audit Report No. 82-21, Audited March 24-30, 1982.
Audit Review approved May 11, 1982.
--
PT 652.001, Power Range Reactor Recirc Flew Units
Audit Report No. 82-15, Audited February 23, 1982.
Audit Review approved March 1, 1982.
--
414.001A-1, B-1, C-1, Diesel Generator Room Ventilation System
Audit Report No. 81-19, Audited June 3, 1981.
Audit Review approved June 19, 1981.
..
.. .
_ _ _ _ _ _ _ _ _ _ _ .
.
.
1
Long Island Lighting Company
10
PT 315.001C, 125 VOC Power Distribution
--
Audit Report No. 81-14, Audited May 14, 1981.
Audit Review approved May 19, 1981.
--
PT 107.002, Demineralized Water Transfer
Audit Report No. 82-14, Audited January 13 to
February 17, 1932
Audit Review approved February 19, 1982
--
PT 41J.001, B-2 Screenwell Pumphouse Ventilation
Audit Report No. 82-19, Audited April 22, 1982
Audit Review approved April 22, 1982.
--
PT 707.001-1, Fuel Pool Coolina and Cleanup
Audit Report No. 82-16, Audited March 11, 1982.
Audit Review approved April 1, 1982.
.
--
PT 311.001 A, B, C, 480V Emergency Power Distribution
Audit Report No. 81-23, Audited December 14, 1981.
Audit Review approved December 15, 1981.
The inspector reviewed the above preoperational test procedure
packages and verified that they met the acceptance criteria of
the test procedures, FSAR documents and applicable regulatory
requirements.
The inspector had no further questions.
5.
Unresolved Items
Unresolved items are matters about which more information is required
to ascertain whether they are acceptable items, items of noncompliance,
or deviations. An unresolved item disclosed during the inspection is
discussed in Section 4.4.2.
6.
Plant Tours
The inspector made several tours of the facility during the course of
the inspection. The tours included the containmant, reactor building,
turbine building, control structure, control room, battery rooms and
diesel generator rooms. The inspector observed work in progress,
.
housekeeping, cleanliness controls and witnessing of tests.
No
discrepancies were identified.
7.
Exit Interview
At the conclusion of the site inspection on May 20, 1982, an exit
meeting was conducted with the licensee's senior' site representatives
(denoted in Paragraph 1).
The inspector summarized the scope and
findings of the inspection.
Previous inspections in this area were
discussed.
d
y
-- ,- -
.. ,,-
w.
- *
I
.
.
1
ATTACHMENT A
PREOPERATIONAL TEST PROCEDURES REVIEWED
PT 102.001-1, approved August 25, 1981. Test results evaluation
--
approved November 10, 1981. Circulating Water
--
PT 107.001-3 approved January 26, 1979. Test results evaluation
approved October 22, 1981. Makeup Demineralizer and Transfer
--
PT 117.001-3 approved April 20, 1977.
Test results evaluation approved
.
March 20, 1980.
Instrument and Service Air
PT 123.001-1 approved September 4, 1981. Test results evaluation
--
approved February 26, 1982.
--
PT 129.001 approved January 21, 1981. Test results evaluation approved
May 3, 1982. Turbine High Pressure Control
--
PT 136.004 approved September 27, 1978. Test results evaluation
approved March 12, 1982. Jet Pump Instrumentation
--
PT 501.002 approved December 14, 1981. Test results evaluation approved
March 30, 1982.
Remote Shutdown Panel Room Total Flooding Halon
--
PT 315.001A approved July 25, 1979. Test results evaluation approved
October 22, 1980.
125 VDC Power Distribution A
--
PT 315.001B approved July 25, 1979. Test results evaluation approved
June 26, 1981. '125 VDC Power Distribution B
--
PT 316.001A approved June 20, 1979. Test results evaluation approved
August 26, 1980. 24 VDC Power Distribution A
--
PT 316.001B approved June 20, 1979. Test results evaluation approved
September 17, 1980.
24 VDC Power Distribution B~
PT 311.001A approved November 14, 1978. Test results evaluation
--
approved December 14, 1981.
480 V Emergency Bus Distribution A
PT 311.001B approved November 14, 1978. Test results evaluation
--
approved December 14, 1981. 480 V Emergency Bus Distribution B
>
PT 311.001C approved November 14, 1978. Test results evaluation
--
approved December 14, 1981. 480 V Emergency Bus Distribution C
4
i
.
.
Attachment A
2
PT-410.001A-3 approved April 23, 1981.
Test results evaluation approved
--
June 4, 1981. Battery Room Ventilation A
PT 410.0018-3 approved April 23, 1981.
Test results evaluation approved
--
June 4, 1981. Battery Room Ventilation B
--
PT.410.001C-3 approved April 23, 1981.
Test results evaluation approved
June 4, 1981.
Battery Room Ventilation C
'PT 414.001A-2 approved May 27, 1981. Test results evaluation approved-
--
June 5, 1981. Diesel Generator Room Ventilation A
--
PT 414.0018-2 approved May 27, 1981. Test results evaluation approved
June 5, 1981. Diesel Generator Room Ventilation B
PT 414.001C-2 apprcved May 27, 1981.
Test results evaluation approved
--
Juen 5, 1981. Diesel Generator Room Ventilation C
--
PT- 415.001A-2 approved February 19, 1982. Test results evaluation
approved March 12, 1982.
Screenwell Pumphouse Ventilation A
--
PT 415.0018-2 approved February 19, 1982.
Test results evaluation
approved March 12, 1982.
Screenwell Pumphouse Ventilation B
--
PT 604.001 approved March 15, 1978. Test results evaluation approved
January 25, 1982. Average Power Range Neutron Monitoring
--
PT 606.001 approved May 19, 1978. Test results evaluation approved
January 11, 1982.
Rod Blocking Monitoring
PT 608.001 approved July 19, 1978. . Test results evaluation approved
--
April 20, 1982. Rod Drive Control
PT 622.001 approved November 9, 1981. Test results evaluation approved
--
February 19,.1982.
Loose Parts Monitoring
--
PT 652.001 approved May 16, 1978. Test results evaluation approved
February 26, 1982.
Power Range Reactor Recirculation Flow Units
PT 654.005-1 approved September 11, 1981. Test results evaluation
--
approved December 22, 1981. Drywell Floor Seal Pressure Monitoring
--
PT 707.001 approved November 9, 1981.' Test results evaluation approved
January 25, 1982.
Fuel Pool Cooling
PT 709.001 approved March 15, 1978. Test results evaluation approved
--
March 30, 1982. Reactor Water Cleanup
PT 717.001 approved November 25, 1980.
Test results evaluation approved
--
May 21, 1981.
Liquid Radwaste Discharge Sample Tanks
I
--
PT 710.001 approved November 19, 1980. Test results approved April 9, 1981.
Low Conductivity Liquid Radwaste
. - . .
.
.
.
.
Attachment A
3
--
AT 000.005 approved July 23, 1980. Test results evaluation approved
July 27, 1981.
Cathodic Protection - Diesel Oil Tank and Landside
Screenwell Areas
AT 000.006 approved July 23, 1980. Test results evaluation approved
--
July 30, 1981.
Cathodic Protection - Waterside Structures
--
AT 000.007 approved September 18, 1980. Test results evaluation
approved August 10, 1981.
Condenser Cathodic Protection
--
AT 105.001-2 approved October 26, 1977. Test results evaluation
approved January 23, 1981. Condensate Storage and Transfer
AT 113.001 app.oved May 9, 1978.
Test results evaluation approved
--
January 23, 1981.
Stator Cooling System
--
AT 131.001-2 approved December 17, 1976.
Test results evaluation
approved August 16, 1978. Well and Domestic Water
--
AT 301.001 approved June 17, 1980. Test results evaluation approved
May 2, 1981.
138 KV System
AT 302.001 approved March 12, 1980. Test results evaluation approved
--
June 12, 1980. 69 KV System
AT 303.001 approved January 17, 1980.
Test -esults evaluation approved
--
January 6,1981. Main Generator Transformers
--
AT 304.001-1 approved October 18, 1979. Test results evaluation
approved November 14, 1980.
Normal Station Service Transformer
--
AT 305.001 approved October 18, 1979.
Test results evaluation approved
August 4, 1980.
Reserve Station Service Transformer
--
AT 313.001A-1 approved April 28, 1978. Test results evaluation approved
May 12, 1980.
120 VAC UPS Inverter R36-INV-01
--
AT 313.001B-1 approved April 28, 1978. Test results evaluation approved
June 12, 1980.
120 VAC UPS Inverter R36-INV-02
AT 318.001-1 approved December 11, 1980. Test results evaluation
--
approved July 27, 1981.
120 V AC-DC Lighting
--
AT 411.001-1 approved August 24, 1977.
Test results evaluation approved
August 5, 1980. Chemical Lab Heating, Ventilation and AC
AT 416.001-2 approved November 29, 1980. Test results evaluation
--
approved October 8, 1981.
Radwaste Building Ventilation
--
AT 670.003 approved January 8,1980.
Test results evaluation approved
October 15, 1980.
120 VAC UPS Inverter
.
_ _ _ _ _ , _ _
__
,
.,
- _
_. -
..
0
Attachment A
4
AT 670.004 approved December 14, 1979. Test results evaluation approved
- --
January 13, 1981.
125 VDC Power to Inverter
'
AT 708.001-1 approved March 16, 1978. -Test results evaluation approved
---
January 14, 1982.
Fuel Pool-Suppression Pool Cleanup
--
AT 715.001 approved September 18, 1980. Test results evaluation
approved November 17, 1981. Auxiliary Boiler Sample Panel
^
AT 715.005 approved' August 27, 1980. Test results evaluation approved
'
--
August 20, 1981. Hypochlorination Sampling
AT 422.001-1-approved January 8, 1981. Test results evaluation approved
--
October 25, 1981.
Hot Water Heating and Glycol System
AT 114.001 approved November 7, 1979.
Test results evaluation approved
--
,
November 12, 1979. Generator Isolate Phase Bus Cooling
i
--
AT 125.001-1 approved December 29, 1977. Test results evaluation
approved August 12, 1981.
Sealing Water System
,
1
4
s
9
- __ ,
. ~ . ._ _ - - - . -
_
,_ . - , . _
__
,-
,
,m
--.4
--.. -
- .
.y..
-
.~-