ML18152A429
| ML18152A429 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/30/1990 |
| From: | Hunt M, Mark Miller NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18152A430 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 50-280-90-22, 50-281-90-22, NUDOCS 9009240235 | |
| Download: ML18152A429 (16) | |
See also: IR 05000280/1990022
Text
Report Nos. :
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, N.W.
ATLANTA, GEORGIA 30323
50-280/90-22 and 50-281/90-22
Licensee: Virginia Electric and Power Company
Glen Allen, VA
23060
Docket Nos.:* 50-280 and 50-281
Facility Name:
Surry 1 and 2
Inspection Conducted:
July 9-19, 1990
Inspector:
(Vj e*
A)
fr} Jt.0
License Nos.: DPR-32 and DPR-37
M. N. Miller, Reactor Inspector
Approved by:
~ ~,
M. D .unt :Actigchle
Plant Systems Section
Engineering Branch
Division of Reactor Safety
SUMMARY
Scope:
Diite Signed
?{)3o[1b
Date Signed
This special, announced inspection was conducted in the areas of the licensee's
conformance to Regulatory Gui de (RG) 1. 97, Instrumentation For Light-Water
Cooled Nuclear Power Plants To Assess Plant And Environs Conditions During
And Following An Accident.
Results:
In the areas inspected, one deviation was identified.
The licensee was not in full compliance with the design and qualification
criteria for instrumentation in Regulatory Guide (RG) 1.97, Revision 3.
One
deviation with two examples was identified.
Isolators are not installed and
the indicators are not seismically qualified.
Several weaknesses were
identified in the calibration program concerning the multiplexers and
wattmeters.
The Equipment Qualification List was not complete and up to date,
also several instruments were incorrectly listed.
The licensee stated that a
submittal would be sent to NRR to address the RG 1.97 criteria for recorders in
accordance with their emergency operating procedures.
Overall, the licensee's
RG 1.97 program was not considered to be acceptable for full compliance with
RG 1.97 criteria.
Deviation
The instrumentation does not meet the RG 1.97 design and qualification criteria
in the Equipment Qualification Section and the Interfaces Section.
Several
indicators and recorders for Category 1 variables are commercial grade items
9009240235 900906
ADOCK 05000280
f"\\
Pl\\11 I
2
that do not have seismic qualification. Isolation devices are not installed as
interfaces between the RG 1.97 indicators/recorders and the non Class IE plant
computer. This is identified as Deviation 50-280/281/90-22-0l, Instrumentation
Does Not Meet RG 1;97 Design And Qualification Criteria.
Strenaths
The Quality Assurance Department performed an audit identifying findings not in
compllance with RG 1.97 which resulted in followup action projects by
engineering.
The licensee performs loop calibrations except for the multiplexers.
The Electrical Maintenance Department implemented appropriate corrective action
for items identified during the maintenance team inspection.
Weaknesses
The Equipment Qualif_ication List is incomplete and items are not correctly
listed.
The Equipment Qualification List standard does not address isblation devices
for instrumentation.
The calibration program does riot include loop calibration for multiplexer
signals.
The Emergency Response Facility/Safety Parameter Pi splay System computer does
not identify RG 1.97 instrumentation in all the display groups.
The wattmeters for -the "pressurizer heater status" variable are not in the
-calibration program *.
The. deviation, the strengths, and the weaknesses are discussed in
Paragraph 2.b.
..
REPORT DETAILS
1.
Persons Contacted
_Licensee Employees
- T. Abercrombie, I&C Engineer
- D. L. Barron, I&C Engineer
- W.R. Benthall, Supervisor, Licensing
- R. C. Bilyen, Licensing Engineer
- F. F. Caufield, Staff Engineer
- M. W. Duda, Senior Staff Engineer
- D.S. Hart, Supervisor, Quality
- M. Kansler, Station Manager
- R. K. MacManus, Supervisor, ISI/NDE Engineering
- W. T. McBride, Supervisor, Electrical Engineering
- J. A. Price, Assistant Station Manager
- G. W. Thompson, Supervisor, Maintenance Engineering
- E. F. Watts, Supervisor, Electrical Engineering
Other licensee employees contacted during this inspection included
engineers, operators, technicians, and administrative personnel.
NRC Resident Inspector
- W. E. Holland, Senior Resident Inspector
- Attended exit interview
2.
Inspection of Licensee I s Implementation of Multi pl ant Acti'on Item A-17:
Instrumentation for Nuclear Power Plants to Assess Plant and Environs
Conditions During and Following an Accident (Regulatory Guide 1.97)
(25587)
.
Criterion 13, "Instrumentation and Control 11, of Appendix A to 10 CFR
Part 50 includes a requirement that instrumentation be provided to monitor
variables and systems over their anticipated ranges for accident
condi ti ans as appropriate to ensure adequate safety.
Regulatory
Guide 1.97 describes a method acceptable to the NRC staff for complying
with the Commission's regulations to provide instrumentation to monitor
plant variables and systems during and following an accident.
The licensee responded to RG 1.97 (NUREG 0737, Supplement 1) in letters
dated January 31, 1984; May 10, 1985; June 21, 1985; August 2, 1985;
April 21, 1986; and August 12, 1987.
The Safety Evaluation Reports for
RG 1. 97 were issued in December 1987 and March 1988.
..
2
The SER dated March 1988 concluded that the licensee's instrumentation for
RG 1.97 either conforms to or is justified in deviating from RG 1.97,
Revision 3 with the exception of addressing the variable, containment sump
water temperature.
The containment sump water temperature variable will
remain open pending the outcome of the staff's generic review of the need
for environment qualification.
In Section 2.0, Evaluation Criteria, of
the SER, it is specifically stated that regional meetings were held in
February and March 1983 to answer licensee questions and concerns.
At
these meetings the NRC po 1 icy for RG 1. 97 was es tab l is hed that the NRC "
would only address exceptions taken to RG 1.97.
Further, where licensees
explicitly state that the instrumentation system conform to the
provisions, no further staff review would be necessary for those items.
Therefore, the review performed and reported by the SER only addresses
exceptions to the guidance of RG 1. 97.
This is further discussed in
Paragraph 2.b.
This inspection assessed the licensee's RG 1.97 instrumentation program
using (1) the design and qualification criteria described in Table 1 of
RG 1.97, Revision 3; (2) the Technical Evaluation Report No. EGG-EA-6799
dated November 1987, Conformance .to Regulatory Guide 1.97 Surry 1 and 2;
(3) the licensee's submittals as discussed previously; and (4) 10 CFR
Part 50.
A random sample of 23 vari ab 1 es from the 1 i censee
I s submi tta 1 were
selected to evaluate the licensee's program.
The variables selected were
classified as Category 1 and 2 which have the most stringent design
requirements of all RG 1.97 instruments. The instruments examined and the
results achieved are discussed in the paragraphs and tables below.
a.
Category 1 and 2 Instruments
The instrumentation listed in the following Tables was examined to
verify that the design and qualification criteria for RG 1.97, the
SER and licensee commitments had been satisfied. The instrumentation
was inspected by reviewing drawings; procedures, data sheets and
other documentation; and performing walkdowns for visual observation
of selected installed equipment including control room indicators and
recorders.
The following areas were inspected:
(1)
Equipment Qualification - The EQ Master Equipment List, Q-list,
I&C List, and instrument drawings were reviewed for confirmation
that the 1 i censee had addressed environmental qua 1 i fi cation
requirements and seismic qualification.
An example of the
deviation in this area is discussed in Paragraph 2.b.
( 2)
Redundancy -
Wa 1 kdowns were performed . to verify by visual
observation that selected instruments were installed as
specified and that separation requirements were met.
In
ategory 1 instrumen-
3
(3)
Power Sources - Wiring drawings were reviewed to verify the
instrumentation is energized from *a safety-related power source
if applicable.
(4)
(5)
( 6)
(7)
(8)
(9)
Note
Display and Recording - Walkdowns were performed to verify by
visual observation that the specified display and recording
instruments were installed.
Wiring drawings were reviewed to
verify there was at least one recorder in a redundant channel
and two indicators, one per division (channel) for each measured
variable. A concern in this area is discussed in Paragraph 2~b.
Range - Walkdowns were performed to verify the actual range of
the indicator/recorders was as specified in RG 1.97 or as stated
in the licensee
1s submittal.
Review of calibration procedures
verified sensitivity and overlapping requirements of RG 1.97 for
instruments measuring the same variable.
Interfaces - The wiring drawings, I&C List, and Q-list were
reviewed to verify that safety-related isolation devices were
used when required to isolate the circuits from non-safety
systems.
An example of the deviation in this area is discussed
in Paragraph 2.b.
Direct Measurement - Wiring drawings were reviewed to verify
that the parameters are directly measured by the senors.
Service, Testing, and Calibration - The maintenance program for
performing ca 1 i brat ions and survei 11 ances was reviewed and
discussed with the licensee.
Calibration and surveillance
procedures and the latest data sheets for each instrument were
reviewed to verify the instruments have a val id calibration.
Two weaknesses were identified in this area as discussed in
paragraph 2.b.
Equipment Identification - Walkdowns were performed to verify
that Types A, Band C instruments designated as Categories 1 and
2 were specifically identified with a common designation on the
control panels.
A weakness was idtntified in this area and is
discussed in paragraph 2.b.
Instruments in this report are applicable to both units
that have a X in their identification number .
~--~-
4*
TABLE 1
CATEGORY 1 INSTRUMENTS
Variable
Steam Line Pressure
_ (S/G)
Refueling Water
Storage Tank Level (RWST)
Condensate Storage Tank
Level (CST)
RCS Hot Leg Temperature
Instrument Number
MS-PT-X-474
MS-PI-X-474
MS-PT-X-475
MS-PI-X-475
MS-PT-X-476
MS-PI-X-476
MS-PT-X-484
MS-PI..:X-484
MS-PT-X-485
MS-PI-X-485
MS-PT-X-486
MS-PI-X-486
MS-PT-X-494
MS-PI-X-494
MS-PT-X-495
MS-PI-X-495
ERF/SPDS Computer
CS-LT-XOOA
CS-LI-XOOA
CS-LT-XOOB
C_S-LI-XOOB
CS-LT-XOOC
CS-LI-XOOC
-CS-LT -XOOD
CS-LR-XOO
ERF/SPDS Computer
CN-LT-100(200) _
CN-LI-100(200)
CN-LR-100(200)
CN-LT-101(201)
CN-LI-101(201)
RC-TE-X-413
RC-TR-X-413
RC-TE-X-423
RC-TR-X-423
RC-TE-X-433
RC-TR-X-433
ERF/SPDS Computer
ICCM Train A
ICCM Train B
5
TABLE 1
CATEGORY 1 INSTRUMENTS
Variable
RCS Cold Leg Temperature
Core Exit Temperature
Degrees of Subcooling
RCS Pressure [Wide Range]
PORV Position
Pressurizer Level
Steam Generator Level
Narrow Range (S/G)
Instrument Number
RC-TE-X-410
RC-TR-X-413
RC-TE-X-420
RC-TR-X-423
RC-TE-X-430
RC-TR-X-433
ERF/SPDS Computer
RC-TE-1E--51E
ICCM Train A
ICCM Train B
ICCM Train A
ICCM Train B
RC-PT-X-402-1
RC-PI-X-402-1
BC-PT-X-402
RC-PI-X-402
ERF/SPDS Computer
ICCM Train A
ICCM Train B
RC-ZS-PCV-X-455C-Al
RC-ZS-PCV-X-455C-A2
RC-ZS-PCV-X-455C-B1
RC-ZS-PCV-X-455C-B2
RC-ZS-PCV-X-456-Al
RC-ZS-PCV-X-456-A2
RC-ZS-PCV-X-456-Bl
RC-ZS-PVC-X-456-B2
ERF/SPDS Computer
RC-LT-X-459
RC-LI-X-459
RC-LR-X-459
RC-LT-X-460
RC-LI-X-460
RC-LT-X-461
RC-LI-X-461
ERF/SPDS Computer
SG-LT-X-474
SG-LI-X-474
SG-LT-X-475
SG-LI-X-475
. .
(cont'd)
6
TABLE 1
CATEGORY 1 INSTRUMENTS
Variable*
Steam Generator Level
Narrow Range (S/G)
Steam Generator Level
Wide Range (S/G)
Containment Pressure
Intermediate Range
- Containment Sump Level
Wide Range
Auxiliary Feedwater Flow
(Aux. FW)
Instrument Number
SG-LT-X-476
SG-LI-X-476
SG-LT-X-484
SG-LI-X-484
SG-LT-X-485
SG-LI-X-485
SG-LT-X-486
SG-LI-X-486
SG-LT-X-494
SG-LI-X-494
SG-LT-X-495
SG-LI-X-495
SG-LT-X-496
SG-LI-X-496
- SG-L T-X-477
SG-LI-X-487
SG-LT-X-497
SG-LR-X-477
ERF/SPDS Computer
LM-PT-XOOA
LM-PI-XOOA
LM-PT-XOOB
LM-PI-XOOB
LM-PT-XOOC
LM-PI-XOOC
LM-PT-XOOD
LM-PI-XOOD
LM-PR-XOlA
ERF/SPDS Computer
RS-LT-X51A
RS-LIT-X51A
RS-LI-X51A
LM-PR-XOlA
RS-LT-X51B
RS-LIT-X51B
RS-LI-X51B
ERF/SPDS Computer
FW-FT-XOOA
FW-FI-XOOA
FW-FT-XOOB
FW-FI-XOOB
FW-FT-XOOC
FW-FI-XOOC
",
7
TABLE 2
CATEGORY 2 INSTRUMENTS
Variable
Instrument Number
High Pressure Injection
SI-FT-X-940
System Flow (HPI)
SI-FI-X-940
SI-FT-X-943
SI-FI-X-943
SI-FT-X-940A
SI-FI-X-940A
SI-FT-X-943A
SI-FI-X-943A
ERF/SPDS Computer
Low Pressure I~jection
SI-FT-X-945
System Flow (LPI)
SI-FI-X-945
SI-FT-X-946
SI-FI-X-946
Containment Spray Flow
CS-FT-XOOA
CS-FT-XOOB
ERF/SPDS Computer
Pressurizer Heater Status
X-CW-14-H
X-CW-14-J
ERF/SPDS Computer
Accumulator Pressure
SI-PT-X-921
SI-PI-X-921
SI-PT-X-923
SI-PI-X-923
SI-PT-X-925
SI-PI-X-925
SI-PT-X-927
SI-PI-X-927
SI~PT-X-929
SI-PI-X-929
SI-PT-X-931
SI-PI-X-931
ERF/SPDS Computer
Component Cooling Water to
CC-FT-X30A
Engineered Safety Feature
CC-FT-X308
System - Flow
SW-FT-X20A
SW-FT-X208
ERF/SPDS Computer
(cont'd)
8
TABLE 2
CATEGORY 2 INSTRUMENTS
Component Cooling Water to
Engineered Safety Feature
System - Temperature
CC-RTD-X25A
CC-RTD-X25B
SW-RTD-XlOA
SW-RTD-X10B
ERF/SPDS Computer
b.
Discussion and Conclusion
The inspector could not verify that Surry has implemented a
satisfactory program to be either in full compliance with or meet the
intent of RG 1. 97.
Based on the SERs and the NRC policy for only
addressing exceptions to RG 1.97 as previously discussed in
Paragraph 2; the licensee's submittals; the licensee's SQA Audit
89-01; and the licensee's Technical Report No. PE-0014, Revision 0,
dated December 19, 1989; and the deviation and weaknesses identified
during the inspection; the inspector concluded the licensee was not
in full compliance with RG 1.97.
A brief discussion of the areas
reviewed and the results, the NRC concerns, the deviation, the
weaknesses, and the licensee's planned action are summarized below.
(1) Calibration
The inspector reviewed the latest calibration data sheets for
those RG 1.97 instruments and loops identified in Tables 1 and
2.
The inspector noted that loop calibrations are performed and
this is considered a strength in the licensee's program.
However, several weaknesses were also identified and are listed
as follows:
Wattmeters X-CW-14-H and -J were installed to monitor the
Category 2 variable "Pressurizer Heater Status".
These
instruments were calibrated during the plant modifications and
are still in a valid calibration period.
However, the licensee
had not developed a calibration procedure for periodic
calibration requirements and had not 1 isted them in the
preventive maintenance (PM) calibration program.
The licensee
has stated calibration procedures will be developed and the
instruments will be listed in the PM calibration program.
This
will be accomplished for use during the next refueling outage
for each unit.
The ERF/SPDS Computer System monitors and displays the RG 1.97
variables in the emergency response facility (ERF) and in the
control room for both Units.
The signals from the RG 1.97
instruments and loops are transmitted to the ERF/SPDS computer
system and the ICCM systems through a Cl ass lE multiplexer-
isolator system.
This multiplexer is not calibrated during the
.
l
.
(2)
9
instrument loop calibration. It is calibrated as an individual
instrument with the loop instruments disconnected. There is no
overlap testing performed as defined in IEE Standard 338, IEEE
Standard Criteria for the Periodic Testing of Nuclear Power
Generating Station Safety Systems.
A channel check is
performed.
The ERF/SPDS computer is not a Class lE system.
However, the ICCM system is Class lE and safety-related.
The
licensee has been aware of this weakness and is in the process
of including loop calibration for the multiplexer in the new
calibration procedures to be written in the Procedure Upgrade
Program (PUP).
The PUP is not expected to be completed until
the end of 1995. * The inspector considered that the calibration
of safety-related signals to the multiplexer and ICCM system was
not satisfactory.
The licensee agreed and stated the existing
procedures for calibrating safety-related signals to the
multiplexer-ICCM system would be modified *to include loop
calibration requirements.
This will be accomplished for use.
during the next refueling outage for each unit.
Q-list
The inspector reviewed the Q-list for the RG 1.97 instrumenta-
tion.
Numerous examples of items were either incorrectly
identified or missing from the Q-list in accordance with the
Q-list standard, STD-GN-0003, Revision 1, Instructions For
Identifications and Classification of Safety-Related Structures*,
Systems, and Components.
The 1 i censee informed the inspector
that the Q-list up grade is not scheduled for completion until
December 1992.
However, the inspector did not identify any
evidence that the RG 1.97 program addressed* reviewing and
correcting the Q-list in accordance with the QA program.
The licensee's Technical Report No. PE-0014 for RG 1.97, Section
5.5, Quality Assurance, states that" ****. there are not* any
specific criteria unique to instrumentation that needs to be
addressed in more detail.
11
The report implies that the RG 1.97
instrumentation meets the criteria of the QA program. * The
inspector identified the following examples that needed to be
addressed:
Variable
Instrument Number
Problem
RWST Level
CS-LR-XOO
Missing
CST Level
CN-LR-XOO
Missing
RCS Cold Leg
Temperature RC-TE-2410
Missing
..
(cont'd)
(3)
Variable
Pressurizer
Level
Containment
Pressure
Containment
Spray Flow
HP! Flow
Pressure
Flow
Temperature
LPI Flow
10
Instrument Number
RC-1/LR-X-459
LM-PQ-XOOA&B
CS-FT-XOOA&B
SI-FQ-2940A
SI-FQ-2943
SI-FT-2940A
SI-FT-2943
SI-PI-X-921,23,25,27
29 and 31
CC-PQ-X30A&B
CC-RTD-X25A&B
SI-FI-X-945&46
SI-FQ-X-945&46
Problem
Missing
Missing
Missing
Missing
Missing
Missing
Missing
Incorrect
Incorrect
Incorrect
Incorrect
Incorrect
In addition, the signal conditioners (resistor networks) for the
plant computer in all the RG 1.97 instrument loops are not in
the Q-1 i st.
The licensee agreed that the Q-1 i st for RG 1. 97
instrumentation is not correct or up-to-date.
As previously
stated, appropriate corrective action for upgrading the Q-list
for RG 1.97 instrumentation will be completed by the end of
1991.
Interfaces
Part 9, Interfaces, in Table 1, Design And Qualification
Criteria For Instrumentation, in RG 1.97, Revision 3, requires
that
11the transmission of signals for other use should be
through isolation devices that are designated as part of the
monitoring instrumentation *.**
11 At Surry, with the exception of
the RCS pressure loops, the RG 1.97 Category 1 and 2
instrumentation loops transmit their signals to the non-safety
related plant computer without qualified isolators.
No
isolation devices are between the RG 1.97 monitoring displays
and the plant computer.
This is identified as an example of
Deviation, 50-280/281/90-15-0l, Instrumentation Does Not Meet
RG 1.97 Design And Qualification Criteria.
11
(4)
Equipment Qualification
Part 1, Equipment Qualification, in Table 1, Design And
Qualification Criteria For Instrumentation, RG 1.97, Revision 3
states that "qualification applies to the complete instrumenta-
tion channel from the sensor to display *** " It further states
that the seismic portion of qualification should be in
accordance with RG 1.100, Seismic Qualification of Electric
Equipment for Nuclear Power Plants.
At Surry, commercial grade
indicators and recorders are used in the RG 1.97 instrumentation
loops. These unqualified commercial grade instruments are Hagan
107. indicators and Westinghouse Optimac 101 recorders.
The
specific list of indicators and recorders is in the licensees
submittal dated January 31, 1984.
The use of non-seismically
qualified indicators and/or recorders in RG 1.97 Category 1
instrumentation loops is identified as the second example of
Deviation
50-280/281/90-22-01
discussed
previously
in
Paragraph 2 (3), Interfaces.
(5)
Display and Recording
RG 1.97 requires Category 1 variables have continuous real-time
display.
This may be a dial, digital display, CRT, or
stripchart recorder. If direct and immediate trend or transient
information is essential for operator information or action, the
recording should be continuously available on redundant
dedicated recorders. Otherwise, it may be continuously updated,
stored in computer memory, and displayed on demand.
The
licensee's initial position was the ERF/SPDS computer met this
requirement.
However, the inspector pointed out the ERF/SPDS
computer did not meet the Cl ass lE power requirement for
Category 1 variables.
The licensee agreed.
The inspector
requested the EOPs be reviewed to determine trend and transient
information requirements for the four variables listed below.
The licensee's response was as follows:
Variable
S/G Pressure
RCS Wide Range Pressure
Auxiliary FW Flow and
Neutron Flux
Response
Recording instrumentation
will be added in accordance
with EOP requirements
Use ICCM Displays
Not required by EOP, no
recorder
The inspector did not find the licensee's position to be
acceptable except for the S/G pressure variable.
The licensee
stated that a submittal would be sent to NRR by September 30,
~-------------------------------~--------
'
t
3.
12
1990, to address this concern.
The submittal would contain the
licensee's position discussed in this paragraph for the above
variables for NRR review.
(6)
ERF/SPDS Computer System
The inspector examined the ERF/SPDS computer system to determine
how the RG 1.97 variables are displayed and what type of unique
identification is used.
The computer system has two methods to
display RG 1.97 variables.
For RG 1.97 variables that do not
have any other display means such as an indicator or recorder,
these variables are displayed specifically in two groups
identified as RG 1.97 variables.
These groups are Group 97 for
Unit 1 and Group 98 for Unit 2.
Each group has approximately 42
analog variables such as containment spray flow, CCW to ESF flow
and temperature, vital -bus voltages, and 38 digital variables
for position switches.
The second method used to display
RG 1.97 variables (which have other display means) not displayed
in_Groups 97 and 98 .is to display them in the system groups.
For example, pressurizer level is displayed in the RC system
group.
The method for displaying these RG 1.97 variables in the
system groups without an unique identifier is identified as a
weakness.
The licensee stated appropriate corrective action to
provide the RG 1.97 unique identification for all variables in
the ERF /SPDS computer system wi 11 be completed by the end of
1990.
.
(7) Corrective Action
During the maintenance team inspection, the team i den ti fi ed
weaknesses in the electrical area.
These weaknesses were with
switchgear, where spare leads were not properly capped, wires
were frayed, and hardware was missing (bolts, nuts, washers,
te.rminal covers).
The inspector reviewed 12 completed work
orders verifying * the licensee completed the appropriate
corrective action.
The inspector considered this a strength
with the electrical maintenance group.
IE Bulletin No. 84-02 Follow Up
(Closed) IE Bulletin No. 84-02, Failure of General Electric Type HFA
Relays Used in Class lE Safety Systems.
NRC Inspection Report 87-21
stated that:
11A review of the status was conducted by the licensee and
they determined that the original response to this bulletin, dated
July 31, 1984, was incorrect in that eight relays per unit were not
identified as candidates for replacement.
This omission prevented these
relays from being inspected and subsequently replaced as required by the
bulletin.
The licensee is in the process of preparing a revised response
to the bulletin.
11
r
t
~-------
13
NRC Inspection Report 88-33 stated that "the inspection effort .** reviewed
the circumstances involving the licensee original response, dated July 31,
1984, and a subsequent revision to the response dated September 4, 1987."
These circumstances detailed in the report are that the licensee had
para 11 el efforts at the station and corporate office for the original
response to the bu 11 et in.
However, the input from the stat ion was not
incorporated. This condition went undetected until the licensee responded
to a General Electric Service Advisory Letter, dated November 14, 1986,
involving the same relays.
A similar search discovered these relays.
This error was officially identified in a licensee's internal memorandum
dated June 30, 1987.
At this time the licensee performed a full drawing
review and field walkdown to determine if all relays had been identified
as having been omitted.
Therefore, the licensee submitted an amended
response to the bulletin dated September 4, 1987, listing the additional
eight relays per unit that were omitted from the original response.
The
regional staff had determined the licensee
I s amended response and
corrective action satisfy the requirements in Bulletin 84-02.
This item
is closed.
4.
Exit Interview
The inspection scope and results were summarized on July 19, 1990, with
those persons indicated in paragraph 1.
The inspector described the areas
inspected and discussed in detail the inspection results summarized below.
Proprietary information is not contained in this report.
Dissenting
comments were received from the licensee regarding the unresolved items
which were later upgraded to a deviation.
The licensee stated the following corrective actions will be
taken in response to the inspection findings:
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0
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Calibration procedures will be developed for the wattmeters
used for the variable "pressurizer heater status
11 and
listed in the PM calibration program for implementation
during the next refueling outage for each unit.
The existing calibration procedures for instruments
transmitting signals through the multiplexer to the ICCM
will be modified to include loop calibration requirements
for the ICCM system.
This wi 11 be completed for
implementation during the next refueling outage for each
unit.
The ERF/SPDS computer system display will be upgraded to
provide a unique identifier for all RG 1.97 instruments.
This will be completed by the end of 1990.
The Q-1 is t wi 11 be upgraded (corrected) for a 11 RG 1. 97
instrumentation.
This will be completed by the end of
1991.
, ..
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14
A submittal will be made to NRR by September 30, 1990 to
address the licensee's position concerning the RG 1. 97
criteria for "Display and Recording" for the Category 1
variables S/G pressure, neutron flux, RCS pressure and
auxiliary FW flow.
The licensee stated recording
instrumentation wi 11 be added in accordance with EDP
requirements for the S/G pressure.
The inspector stated that the licensee's RG 1. 97 program was not
considered acceptable and he could not verify the licensee fully
complied with or met the intent of RG 1. 97, the SERs, and the
licensee '.s submittal s.
Two unresolved items were identified during the inspection
and discussed with the licensee.
The two unresolved items have
been upgraded as the examples for Deviation 50-280/281/90-22-01.
Mr. A. Price of your staff was inform August 24, 1990 that the
two unresolved items are now a deviation.
5.
Acronyms and Initialisms
ccw
ERF/SPDS -
FI
FR
FT
ICCM
LR
LT
LP!
NRC
PR
Q
Q-List
S/G
Component Cooling Water
Emergency Response Facility
ERF/Safety Parameter Display System
Environmental Qualification
Engineered Safety Features
Flow Indicator
Flow Recorder
Flow Transmitter
High Pressure Injection
Instrumentation and Control
Inadequate Core Cooling Monitor
Level Indicator
Level Recorder
Level Transmitter
Low Pressure Injection
Power Operated Relief Valve
Nuclear Regulatory Commission
Nuclear Reactor Regulation (NRC)
Pressure Indicator
Pressure Recorder
Pressure Transmitter
Power Supply for Flow, Level or Pressure
Quality Assurance
Equipment Qualification List
Regulatory Guide
Resistance Temperature Detector
Safety Evaluation Report
Temperature Element