IR 05000317/1990005
| ML20034B059 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 04/17/1990 |
| From: | Cowgill C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20034B056 | List: |
| References | |
| 50-317-90-05, 50-317-90-5, 50-318-90-05, 50-318-90-5, NUDOCS 9004250271 | |
| Download: ML20034B059 (56) | |
Text
.
,
,
.
.
.
t U.S. NUCLEAR REGULATORY COMMIS$10N
!
REGION I
!
50-317/90-05
Report Nos.:
50-31B/90-05 DPR-53 License Nos.: DPR-69
Licensee:
Baltimore Gas and Electric Company Post Office Box 1475 Baltimore, Maryland 21203 Facility:
Calvert Cliffs Nuclear Power Plant, Units 1 and 2
!'
Location:
Lusby, Maryland Dates:
February 11, 1990 - March 24, 1990
,
Inspectors:
James Beall, Senior Resident Inspector (2/11-27/90)
Larry Nicholson, Senior Resident Inspector (2/28-3/24/90)
Allen Howe, Resident Inspector
Tae Kim, Resident Inspector Donald Caphton, Senior Technical Reviewer
'
Jennifer Dixon, Reactor Engineer Larry Scholl, Resident Inspector - Limerick William Oliveira, Reactor Engineer i
Donald Taylor, Reactor Engineer Henry athrop, Reactor Engineer
)r-/
4!M Approved by:
k
/
o
.
Curtfs J. y wgill,g hief
/ Daf e'
Reactor Pr6jects Hetion No. IA Division of Reactor Projects Inspection Summary.
,
,
.
Areas Inspected:
This report documents a routina safety inspection by the resident inspectors and accompanying regional inspectors.
Areas reviewed included:
plant operations, radiological protection, surveillance and main-tenance, safety assessment and quality verification, and followup of previous inspection findings and restart issues. A summary of the results of a meeting =
with NRC Region I and BG&E management on March 21, 1990 is also discussed.
,
9004250271 900418 FDR ADOCK 03000317 O
.
,-
.
' Inspecticn Summary (C ntinued)
ik
,
Results:
The results of this inspection have indicated that the licensee is making sufficient progress in addressing the issues which are to be resolved prior to restart. The licensee has exhibited safety-consciousness and conser-vatism in its efforts to physically ready the plant for restart and to effect appropriate changes in procedures and procedural controls to address previously noted problem areas.
There were no violations or deviations noted as part of this inspection. An Executive Summary follows.
l
--
.
.
.
.
.
'
.
,
EXECUTIVE SUMMARY i
i Plant Operations:
At Calvert Cliffs Unit 1, inspection effort focused on the assessment of plant readiness for restart.
Both routine and backshift plant tours and system walkdowns revealed that the plant is in an acceptable physical
condition for restart.
While the inspector system walkdowns revealed a few
!
valve lineup and pipe support discrepancies, the licensee's corrective actions in response to the noted concerns were acceptable and associated systems were
operationally ready for restart. The inspectors noted that control room oper-
!
ators responded quickly and effectively to an inadvertent ESF actuation with
!
safety injection which was caused by ESC technicians while performing RPS func-tional testing.
Followup actions (documentation, root cause analysis, correc-tive actions to prevent recurrent) were adequate.
'
Additional licensee effort is needed to assure that both units can be shut down
!
in the event of a design basis Appendix R fire. While the existing procedures
,
and staffing are adequate for remote shutdown of. Unit 1, controls and staffing
considerations for dual ~ unit remote shutdown have not been completely resolved and the remote shutdown of both units has yet to be validated.
The progress of the Procedures Upgrade Program (PUP) has been satisfactory to support startup and safe operation of Unit 1.
However, certain elements of the program were either being revised or were not complete.
The inspectors will continue to closely monitor PVP implementation.
The status of the PUP effort and other CAL response ef forts which are still in progress will be provided by
!
the licensee in their submittal of Revision 2 of the Performance Improvement
,
Plan on April 30, 1990.
Radiological protection:
Routine review of this area indicated acceptable per-formance during the inspection period.
Surveillance and Maintenance:
Specific maintenance activities were reviewed during this period in conjunction with an NRC Maintenance Team Inspection
(MTI).
While e inadequacies were identified during resident inspector efforts, a de ailed assessment of this area will be addressed in the MTI Inspection h port (50-317/90-80; 50-318/90-80).
The inspectors noted an inadequacy in a portion of Surveillance Test Procedure STP 0-67-1, Check Valve Operability Test, that dealt with the testing of safety injection tank (SIT) check valves. The procedure did not identify the poten-
,
l tial for creating a particular adverse condition during the performance of the test, i.e.,
a significant RCS cooldown resulting from the addition of cold
water from the SITS. Proper control room operator response compensated for the weak test procedure.
Sufficient progress has been made by the licensee in addressing the previously noted issue of the calibratien of permanently installed instrumentation used for Surveillance Test Procedures to support the operation of Unit.. -
.
.
.
.
Executive Summary (Continued)
- Security:
Review of this area identified no noteworthy findings.
Engineering and Technical Support:
Adequate progress is being made in the resolution of deficiencies noted in the areas of electrical cable separation, anchur bolts for the component cooling heat exchangers, compensatory emergency lighting measures needed for Appendix R Safe Shutdown, and testing of the Salt Water Air Compressor (SWAC) system.
The licensee has committed to perform a review of and install, if necessary, additional emergency lighting needed for Appendix R Safe Shutdown within 6 months of the restart of each unit.
The licensee has also committed to.the development and implementation of a formal operability test program for the Unit 1 SWAC system check valves.
NRC will review the licensee's determination of the adequacy of the component cooling heat exchanger foundation anchor bolts in a future inspection.
Safety Assessment and Quality Verification Plant Operations and Safety Review Committee (POSRC) review of stetion activ-ities was deemed to be adequate. However, an issue remains open with regard to the adequacy of 10 CFR 50.59 screening for temporary modifications.
Effective corrective actions and root cause analysis were noted in the licensee's inves-tigation of an emergency diesel generator trip.
The licensee has made sufficient progress in addressing the corrective action program concerns noted by Readiness Assessment Team Inspection (50-317/89-82)
to support Unit I restart.
The long-term corrective actions program and an interim measure to be taken until that program can be fully developed, the Significant Issues Management System (SIMS) as well as the licensee's new ccm-mitment management system are in the early stages of development.
NRC will closely monitor the licensee's progress in developing and implementing these programs.
.a
.
.
.
e
.
.
.
SUMMARY l
.
l R.E.DENTON
- Conditions leading to letter
- Actions taken in response
!
- Current assessment
- Remaining actions planned j
- Problem identification and Corrective Actions l
l r
'i
.
l
.
SUDt t S.CMT
.
CONDITIONS LEADING TO CAL Control of system status
Control of work activities
'
Procedure use and control-of procedure changes
.
,
'
General background of plant problems
l l
l
.
DUDE 2 4.CH T
,
!
,. -.. _..,., _. _ _ _ _ _ _. _, - -
....-___.,.._......__..,-...-,~......___._.,._.._...._,...-,........--__,.._,.._,...._m_.
-.-...,
--
.
_ _
_ _ -. _. _ _ _ __ _ _ _ _ -_._ __ _
_. _ _ _. _
.,
,
,
,
RESPONSE TO CAL
,
.
i SHORT-TERM ACTIONS i
!
Analyzed root causes
l
'
i Determined detailed corrective action plans
Implemented corrective action plans I
Conducted self-verification of corrective measures i
Documente., closeout -
alties and made these records
.
i
!
available to the NRC for review
'
L
.
,
.
SLIDtil.CHT
'
j
,
l RESPONSE TO CAL
,
LONG-TERM ACTIONS l
,
l
!
Incorporated actions to correct root causes 'into
l Performance Improvement Plan Continuing long-term self-assessment as part of
Performance improvement Plan Verification l
Program
,
L
,
<
, '
l l
'
,
- ;
EL10Ett.CHT
'
- j -
i
.
-
m
-.,-,
,,,,
.-,--,.,-_._,.--,__.--.,.-..,,-.-..,,.,....,..--.,_,-,.---,.-,,,,,,,.---..w..,-
w---,--
- -.
.
-
-
- - - _
.
..
_--
.
'
L'-
ROOT CAUSES I
l l
Emphasis on production and cost control over
safety and quality l
Inadequate procedure resources
-
Insufficient accountability
!
-
'
Concentration or, specific results, not process
-
i i
Weak communications j
.
l
.
!
!
I
i
.uom. cwt
.1
'
'
CURRENT ASSESSMENT
.
- Emohasis on safety and auality first
- Day-to-day decisions now match stated expectations
[
- Policies and procedures now support management
,
i objectives
)
- Q.gatrol of work is satisfactorv j.
- No significant injuries, equipment damage, or schedule setbacks attributhble to poor work j
control since the CAL
- Procedures are now workable or, when required, i
changeable to support plant operations
.o......,
,
.
- -
-
-.. -
-
-
- - - -
-. -
-.
-
...
_
-
....
- -
- -..
- - - - - _ - -. - - -. -
. --
- - - -..
.
...
CONTINUING EFFORTS
.
- 10 of 38 PIP Action Plans are complete, with
'
!
dedicated effectiveness verifications in progress.
l The remaining action plans are continuing.,
{
lssues-Based Planning Process established to
!
identify additional areas requiring improvement
,
t for the Nuclear Program Plan.
l l
- Continuing evolution of plant processes and procedures to support safety and quality, i
i
.
h SLIDt te.C MT
PROBLEM IDENTIFICATION
& CORRECTIVE ACTIONS i
t I
Where we were (RAT)
A variety of methods to identify and track problems
Focus provided on'ly by Startup lasues List
,
i P
h
?
SLl0 E SO.CHT
+
+
. -.
.. _
-
.,
., _
......
-
,,,..._,..,,,_,-#.
,,m.s_
.,_- -,,.+....w.,.-,
,.,
.-,.6
._=
.
.
- - -.-- - -
- -_.- -...________ - _ _ _ _
__-_ _ _
l
...
!
'
PROBLEM IDENTIFICATION
'
-
& CORRECTIVE ACTIOhS
,
l i
i
'
i Where we are j
- Significant issues Management System j
- Modified Flow Path to POSRC
!
!
Pl/CA Systems (with few exceptions) report
to POSRC i
Exceptions are:
- Personnel safety
'
- Plant modifications.(outside ' safety issues * CA)
- NRC-initiated licensing issues
-
Exceptions go directly to Plant Manager
SLID 5 01.CMT
'
.
PROBLEM IDENTIFICATION
-
& CORRECTIVE ACTIONS
Where we are aoino (Short-Term)
Significant issues Management System
Formalize (procedure) flow path to POSRC
Create Significant items List as subset of Commitment
'
Tracking Refine criteria for significant items
.
Institute Phase I of ' Problem Report' System
!
Directed at improving NCR system
-
i
)
!
SLtDa st.CMT -
!
i n, - --..
,-.n-..~...,,--,.
-.,,..,..,,.-,. - - -,,,,.,.,.,,.. -
c
,-., -, + - -,, -
-,..-------,,,,n, a,-r---.,
o.,..
..-a
,w-
._
.
!
-
a
....
PROBLEM IDENTIFICATION j
'
'
-
& CORRECTIVE ACTIONS
.
Where we are coina (Lona-Term)
{
PIP Action Plan for Single Document Approach
(* Problem Report *)
!
'
Will replace Significant lasues Management System -
smooth transition j
Current plan and schedule - Rev. 2 to PIP 04/30/90
.
,
!
!
SLIDE t t.CHT READINESS FOR RESTART
.
R. E. Denton
.
Physical Readiness
Management Readiness
Startup Plan
...
i DLI0t34.CHT i
l l
^
-
.
-
,
9'
)
'
.
READINESS FOR RESTART i
'
'
-
I
'
t
!
I i
-
!
PHYSICAL READINESS
>
'
+ Completed over 1,000 Maintenance Orders since Unit 1 shutdown i
'
i
!
- Conducted comprehensive system walkdowns
.
t
!
Performed several maior material unarades
!
I
- Saltwater instrument Air
-
!
!
- Reinsulation inside containment i
- Motor-Operated Valves
!
Assessed impact / applicability of Unit'2
!
3.
"
l pressurizer leakage e
i Dueses. cat
i
l READINESS FOR RESTART j
i i
"
MANAGEMENT READINESS
- Improvements completed in management processes for
control of system status, work activities, and
procedure usage
- Upgraded corrective action, commitment tracking, and self-assessment processes
- Strengthened the process for setting and communication
'
of management goals, expectations, and accountability
- Implemented plans for further program improvements in the Performance fmprovement Plan
i s
DUDE SS.CMT
>
p h
._,r.._..
, _,. _.., _.., _,....,...
....... _... _ _,, _. _
.......... _ _..,, _.. _ _.... _.
.
_. _.. ~.., _... _... _... _
- -. -. _ -. ~.. -.. -.--. -
-. - - _ _ _ _
_ _ _ _ _ _ _ _ _
_ _ __
i
,
o,.
{
-
STARTUP PLAN
'
'
-
l i
,
,
e Three Elements v
I Plant Readiness for Startup i
-
Startup Contingency and Management
!
-
)
,
Startup Self-Assessment
-
i Complements but does not replace our normal
l organizational processes l
.
i Additional assurance that significant plant and
.
'
process changes made during shutdown are safe and workable during startup and operation
-
SLIDtet.0MT
!
STARTUP PLAN
-i Plant Readiness for Startuo e
- Assure Physical and Management Readiness
- Establishes Startup Review Board
/ Plant Manager - Chair
/ Four Support Managers - Members
- Prescribes plateaus and general criteria
!
to proceed
- Enhanced shift operations organization
t
,
,
SLIDtte.CMT t
>
..,,
,-..,,,m-c..,...
,,,
.,.,.
,-.mm-
.w-m....-,,..4,--.
. - -..
.%mm,
,
,...._
..........-..,.,,-4
_.,u--
,...... - -.., -.
.,
...m-
-
!
,...
'
'
'
STARTUP PLAN i
'
I
?
'
Startuo Continaency & Manaaement Plan
- Compliation of Section and Support Group Plans l
l
- Provides Management Expectailons for Off-Shift.
Coverage and Call-in
i Prescribes Additional Management Support e
t
!
-:
',
euonee. cat
!
.STARTUP PLAN STARTUP SELF-ASSESSMENT
,
Two Major Elements
- Line Organization
- Ind0 pendent Assessment Team
,
Line Organization
.
i l
- Augmentation of in-place process (Job Observation Program, OA/OC Surveillance)
- Real Time Emphasis
- Feedback to Plant Manager 61a Line Management
(Startup Review Board)
Independent Assessment Team
- ISEU Sponsor
- Report to Vice President-Nuclear Energy
-
'INPO-like' observation process suoso. cat
.
i
. _,..,... _, _., _. _
.,.
..
..
. _ _. _.. _ _.,.,.,........
.. -.
,.. _...., _,.., _. _. _ _. _,,..........,. _ _...., -
.. - _ __ _. - _
__ _
.
.
_ _ _ _ _
.
.
.
.
-
,...
SUMMARY l
-
,
.
.
.
'
i G. C. Creel
,
i
Problems leading to issuance of CAL have been identified
,
and addressed
,
Additional actions from STI, RATI, and other NRC
,
inspections have been addressed
!
Implementation of past commitments has been found f
i adequate for restart With the exceptions noted, preparations for restart
are complete
!
'
Finally, BG&E's startup plan will ensure a safe,
,'
j gradual, stepwlse ascension to power operations tu DE 41. Chi
.i l
h f
'
I
!
'
,
s
i
I I
!
$
r i -
.
.
'
-
.
--.- -...... -., - -. -... -
-.. -... -...
. -
.
.
-. -
.
.. -
.. -....... -.
.... -.
-
-