IR 05000302/1989020
| ML19325D108 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/03/1989 |
| From: | Crlenjak R, Holmesray P, Tedrow J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19325D105 | List: |
| References | |
| 50-302-89-20, NUDOCS 8910190014 | |
| Preceding documents: |
|
| Download: ML19325D108 (9) | |
Text
- s
^-
y;a mg r7,
-
.
,
in F
'
f
'
\\'t)
,f
<
,
.,.
W,',',
l~
mm site
'
,
. UNITEO SThTER -
'
,,
.
c if,. I b(n Q' 2 [.
-
. REGION il NUCLEAR RESULATORY COMMISSION'
-
'
~
( 7.6 1 5
-
101 MARIETTA STREET,N.W.
!
' '
ATL ANT A, OLORGI A 30323 '
I
,
,
pT -
'
'
,
- ..
.....+
,
,
l.
,
,
'
>
pp
'
i
"
Report No.:
50-302/89-20.'
.
'
'
j', '
e.
o
- ..
y I
'Liceasee:. Florida Power Corporation '
'
,
'3201 34th Street.. South A.
l r,
,
,
[
St2P.etersburg,FL,33733?
L'
"'
.
a Docket No.: L50-302'
License No.: DPR-72
'
r
.
'
t
-
.,
,
'
Facility Name: ' Crystal River 13
'
.
.o Inspection ConductediTO t15'- September 8s 1989[
.c
' Inspectors 1 M
-
6 ;7<
M-d /4 ?
i 6"
'
'
,
'
/.
,P. Holm455 Ray E5enior ider}t Inspector D~ ate' Signed
,
(,.-
-
y
,
_b/. $p.
1,8k /A9'
b [l.],4 > p
.;
-'
'J..Tedro <
sidept Inspector'
D6te'Sig~ned
-
-
-
,
,,,
Approved by:'
.
A
_
3 87 r
'
R Fate / Sign'ed frlehjak. Sectibn CKief )f tr1 vision of. Reactor Projeetir
<
.
.
'
a
f SUPMARY t
.ap q
>
Scope:~
'
<,
.
<
1W *
This' routine inspei,'....was conducted by two resident inspectors in the areas of-plantL operations, security, radiological' controls. Licensee Event Reports
and Nonconforming Operations Reports,. facility modifications, and licensee'
.
i'
- action:on previous inspection items.
Numerous facility tours were conducted
'
' and facility operations observed.-
Some of.these tours and observations were
'
,
conducted'on backshifts.
,
,
l.
.
Results:
,
L'
'
l One violation was identified:
Failure to follow procedural requirements. and
-
~
,
J
. maintain ' ASV-167 locked; Failure to comply with procedural requirements, l?
paragraphs 2.b and 4.b.(1).
,
-
- l'
i
'
s a
n, 8910190014 891003 PDR ADOCK 0S000302 O
,
M
,
,,
,
,
,
~
p
.
F,
-
.
.
,
,
,
I REPORT DETAILS
.
1.
Persons Contacted Licensee Employees
- J. Alberdi, Manager, Nuclear Plant Technical Support G. Boldt, Vice President Nuclear Production
- G. Becker, Manager, Site Nuclear Engineering Services
- P. Breedlove, Nuclear Records Management Supervisor
- M. Collins, Superintendent, Nuclear Safety and Reliability
- J. Cooper, Superintendent. Technical Support
- A. Friend Nuclear Principal Licensing Engineer R. Fuller, Senior Nuclear Licensing Engineer
'
- B. Hickle, Manager, Nuclear Plant Operations
- H. Koon Assistant Nuclear Maintenance Superintendent
- K. Lancaster, Manager Site Nuclear Quality Assurance
- C. Long, Nuclear Quality Control Supervisor
- G. Longhouser, Superintendent Nuclear Security
- W. Marshall, Nuclear Operations Superintendent P. McKee, Director, Nuclear Plant Operations W.Neuman, Supervisor,InserviceInspection(ISI)
- S. Powell, Supervisor Quality Systems
- S. Robinson, Superintendent, Nuclear Chemistry and Radiation Protection V. Roppal, Manager, Nuclear Operations Maintenance and Outages
- W. Rossfeld, Manager, Nuclear Compliance
.
!
P. Skramstad, Superintendent, Nuclear Chemistry / Radiation Protection
,
- F. Sullivan, Manager, Nuclear Configuration Management E. Welch, Manager, Nuclear Electrical / Instrumentation and Control Engineering Services
- R. Widell, Director, Nuclear Operations Site Support i
p
- M. Williams, Nuclear Regulatory Specialist K. Wilson, Manager, Nuclear Licensing i
Other licensee employees contacted included office, operations, engineering, maintenance, chemistry / radiation and corporate personnel.
- Attended exit interview Acronyms and initialisms used throughout this report are listed in the last paragraph, 2.
Review of Plant Operations (71707)
The plant began this inspection period in power operation (Mode 1).
A l
plant shutdown was commenced on August 25, 1989 to initiate repairs to RWP-2B. The plant remained in Mode 5 for the remainder of the period.
.
...
..
.
..
.
.
.... _ -..... - _.,, _ _ _
__
_. _
-
-
'
a
-
,
-
i
{
-
a o
i i
/
'
'a.
Shift Logs and Facility Records
>
b The inspector reviewed records and discussed various entries with i
-
operations personnel to verify compliance with the Technical t
Specifications (TS) and the licensee's administrative procedures.
The following records were reviewed:
.
Shift Supervisor's Log; Reactor Operator's Log; Equipment
Out-Of-Service Log; Shift Relief Checklist; Auxiliary Building
'
Operator's Log; Active Clearance Log; Daily Operating
Surveillance Log; Short Term Instructions (STI); and Selected
Chemistry / Radiation Protection Logs.
In addition to these record reviews, the inspector independently verified clearance order tagouts.
~
,
No violations or deviations were identified, i
b.
Facility Tours and Observations Throughout the inspection period, facility tours were conducted to observe operations and maintenance activities in progress.
Some operations and maintenance activity observations were conducted during backshifts.
Also, during this inspection period, licensee meetings were attended by the inspector to observe planning and
management. activities.
The facility tours and observations encompassed the following areas: security perimeter fence; control room; emergency diesel generator room; auxiliary building; intermediate building; battery rooms; and, electrical switchgear rooms.
During plant walkdown on September 5, 1989, the inspector noticed that the bypass valve (ASV-167) around the steam inlet valves (ASV-5/204)
to the turbine driven emergency feed pump was not locked in position as required. OP-450. Emergency Feedwater System, valve check list 2, has ASV-167 shown as locked throttled. Valve ASV-167 found unlocked is considered a violation of OP-450.
This is the first example of failure to follow procedural requirements (see paragraph 4.b.(1) for an additional example).
The inspectors also observed conditions in the following areas:
(1) Monitoring Instrumentation The following instrumentation and/or indications were observed to verify that indicated parameters were in accordance with the
-
TS for the current operational mode:
Equipment operating status; area atmospheric and liquid radiation monitors; electrical system lineup; reactor
!
.
.
-
.
-
.
-
- - -
.
...
- - -... -
-.
_
_ _. _. _ _
t v.
.
1* -
t r
.
-
.
.
,
,
!
e
'
- ,
operating parameters; and auxiliary equipment operating parameters.
'
No violations or deviations were identified.
,
(2) Shift Staffing The inspector verified that operating shift staffing was in
c E
accordance with TS requirements and that control room operations were being conducted in an orderly and professional manner.
In
,
addition, the inspector observed shift turnovers on.various
,
occasions to verify the continuity of plant status, operational
!
problems, and other pertinent plant information during these
'
turnovers.
No violations or deviations were identified.
"
(3) Plant Housekeeping Conditions Storage of material and canponents, and cleanliness conditior.s of various areas-throughout the facility were observed to determine whether safety and/or fire hazards existed.
'
No violations or deviations were identified.
_
[
(4) Radiological Protection Frogram
l Radiation protection control activities were observed to verify that these activities were in conformance with the facility
'
policies and procedures, and in compliance with regulatory L
. requirements. These observations included:
,
L Entry to and exit from contaminated areas, including
-
l-step-off pad conditions and disposal of contaminated clothing;.
r Area postings and controls; e
-
Work activity within radiation, high radiation, and
'
-
'
contaminated areas; Radiation Control Area (RCA) exiting practices; and.
-
Proper wearing of personnel monitoring equipment,
-
protective clothing, and respiratory equipment.
Area postings were independently verified for accuracy by the inspector.
The inspector also reviewed selected Radiation Work Permits (RWPs) to verify that the RWP was current and that the controls were adequate.
No violations or deviations were identified.
.
-
. - -
.-
.
.-
.__
_
-
,
,
,
s
-.,..
'
'
y n
.
3 J
,
(5) Security Control
'
P In the course of the monthly activities, the inspector included a review of the licensee's physical security program.
The i
performance of various shifts of the security force was observed in the conduct of daily activities to include: protected and
,
vital area access controls; searching of personnel, packages,
and vehicles; badge issuance and retrieval; escorting of visitors; patrols; and compensatory posts.
In addition, the
inspector observed the operational status of Closed Circuit Television (CCTV) monitors, the Intrusion Detection system in the central and secondary alarm stations, protected area lighting, protected and vital area barrier integrity, and the
,
security organization interface with operations and maintenance.
No violations or deviations were identified.
(6)
Fire Protection Fire protection activities, staffing and equipment were observed i
to verify that fire brigade staffing was appropriate and that fire alarms, extinguishing equipment, actuating controls, fire fighting equipment, emergency equipment, and fire barriers were operable.
.
,
i No violations or deviations were identified.
,
3.
Review of Maintenance (62703) and Surveillance (61726) Activities
Surveillance tests were observed to verify that approved procedtres-were
>
being used; qualified personnel were conducting the tests; tests were adequate to verify equipment operability; calibrated equipment was
-
utilized; and TS requirements were followed.
-
The following tests were observed and/or data reviewed:
- SP '46, EFIC Monthly Functional Test;
- SP-300~ Operating Daily Surveillance Log;
,
- SP-301, Shutdown Daily Surveillance Log; j
- SP-317 RC System Water Inventory Balance; and, i
- SP-421 Reactivity Balance Calculations.
l
'
In addition, the inspector observed maintenance activities to verify that
<
correct equipment clearances were in effect; work requests and fire prevention work permits, as required, were issued and being followed; quality control personnel were available for inspection activities as required; and. TS requirements were being followed.
Maintenance was observed and work packages were reviewed for the following maintenance activities:
Replace operator on DHV-11 in accordance with MP-402A, Maintenance of
-
Limitorque Valve Operator Type SMB-000;
--
.
.
_
.
.:,
i
.
'
.?
-
....
.
[
f
EFP-2 lube oil change in accordance with PM-133. Equipment Lubri-l
-
cation Procedure and Cleanliness Inspection;
MP-150, Maintenance of Raw Water Pumps; and,
!
-
PM-1120 Heat Exchanger Maintenance Inspection / Cleaning /5 hooting
-
and Plugging.
i One violation was identified concerning performance of MP-150 (see
paragraph 4.b.(1)).
4.
Review of Licensee Event Reports (92700) and Nonconforming Operations Reports (71707)
,
a.
Licensee Event Reports (LERs) were reviewed for potential generic impact, to detect trends, ar.d to detennine whether corrective actions appeared appropriate.
Events that were reported immediately were
. reviewed as they occurred to determine if the TS was satisfied.
LERs
'
were reviewed in accordance with the current NRC Enforcement Policy.
(1)
(0 pen) LER 89-23:
This LER reported degraded offsite power and a
failure of the motor driven Emergency Feedwater Pump to start.
The licensee is reviewing offsite power configurations and will develop a surveillance program for relays which initiate
'
emergency feedwater on a loss of offsite power.
The LER will remain open pending completion of the corrective actions.
b.
The inspector reviewed Nonconforming Operations Reports (NCORs) to verify the following:
TS are complied with, corrective actions as identified in the reports or during subsequent reviews have been accomplished or are being pursued for completion, generic items are identified and reported as required by 10 CFR Part 21 and items are reported as required by TS.
NCORs were revie Jed in accordance with the current NRC Enforcement Policy.
..
NCOR 89-207, dated August 28, 1989, reported that a Quality Control hold point for assembly of RWP-2B was missed in procedure MP-150, I
Maintenance of Raw Water Pumps.- Paragraph 4.2.5 states " Check all l
machined mating surfaces' and remove all burrs and foreign matter buildup that could be detrimental to reassembly and gasket sealing.
,
Note any indications on Enclosure 6.
Nuclear Quality Control (NQC)
is to verify that machined mating surfaces are free of burrs and n
l foreign matter.
When the missed hold point was discovered during
'
procedure review for shift turnover, the job was stopped, condition l
of the assembly of the pump was reviewed and the job resumed.
I Failure to make the required hold point inspection is considered to l
be the second example of failure to comply with procedural requircments.
l l
Violation (50-302/89-20-01):
Failure to comply with procedural requirement al n
.
,q,
,,
'.;
,
.
{
i 5.
Followup of O'n-Site Events (93702)
b August 26 -
An Unusual Event (UE) was declared at 0541 due to a T.S.
j:
Required S/D when Raw Water Pump 2B could not be returned
'
'
operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The SRI responded to site and coordinated followup with Region II. The UE was cleared on
August 27,1989, at 1639, when the unit entered mode 5.
The pump was declared inoperable after failing a periodic
.
surveillance-test because of inadequate flow.
Details of this event are contained in NRC Inspection Report
-
50-302/89-24.
-
)
August 28 -
An UE was declared at 0345 on August 28, 1989 due to loss of emergency bus 3A upon failure of the 4160 to 480 stepdown transformers.
The plant was in mode 5 on decay
,
'
heat removal from the "A" train.
The B train was tagged
,
out for work in the B raw water pit associated with the RWP-2B work.
With the loss of the "A" train 480 volt buc, i
decay heat removal was interrupted for about 15 minutes while operators cleared the B train for operation. During this time the reactor coolant system (RCS) warmed from 190 degrees F to 208 degrees F as indicated by the incore data
,
logs.
The RCS was again below 200 degrees' F on B train decay heat removal at T+23 minutes. This unavoidable mode change from mode 5 to mode 4 caused by equipment failure was promptly and properly identified and corrected by the
,
plant operators.
Return to mode 5 was accomplished in the
'
minimum time.
c September 4 - On September 4, 1989 at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> an UE was declared due to greater than one gallon per minute unidentified leakage t
L from the RCS.
The plant was in mode 5 on B train decay heat removal. The laakage was found to be from the B decay heat pump mechanical seal.
Decay heat removal was changed
<
to the A train.
The UE was cleared at 1810.
The senior resident inspector was on-site during this event.
'
6.
1.icensee Action on Previously Identified Inspection Findings (92702 &
a.
(Closed) Violation 302/88-29-01, Failure to have an adequate maintenance procedure for the replacement of a hotleg RTD.
MP-101 was revised to require a leak check at NOT/NOP after
,
replacement.
b.
(Closed) IFI 302/88-29-04, Review the licensee's completion of corrective action fcr placing the RPS in shutdown bypass without resetting the high power reactor trip setpoin F
.
.
.
!.
!. -
,
.
p
,
F
,
L Revision 47 to SP-113 added the requirement for the NSSOD or the reactor engineer to provide the required liigh Flux Trip Setpoint.
l The person providing the setpoint and the setpoint are recorded in the procedure, c.
(Closed) Violation 302/88-29-05, Failure to properly implement
. procedure SP-132.
Paragraph 4.1.6.3 of Al-600, Conduct of Maintenance was revised to require pre-job briefing on refuel evolutions, d.
(Closed) Violation 302/89-06-01, Failure to adhere to the requirements of procedure SP-354A, Monthly Functional' Test of the Emergency Diesel Generator EGDG-1A and OP-707. Emergency Diesel Generator Miscellaneous Activities.
I An operation Study Book (0SB) entry was made emphasizing proper valve control.
OSB documentation was reviewed and all signatures had been made.
s.
(Closed)IFI 302/89-08-01, Review clarifications to procedure PM-112 Heat Exchanger Maintenance Inspection / Cleaning / Shooting and Plugging.
Revision 19 to PM-112 was issued and resulted in a easy to follow procedure.
7.
Exit Interview (30703)
The inspector met with licensee representatives (denoted in paragraph 1)
l at the conclusion of the inspection on September 8,1989.
During this meeting, the inspector summarized the scope and findings of the inspection as they are detailed in this report with particular emphasis on the
,
'
violation.
The licensee representatives acknowledged the inspector's comments and did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspection.
l Item Number Description and Reference 50-302/89-20-01 Violation - Failure to follow procedural I
requirements.
l 8.
Acronyms and Abbreviations CCTV - Closed Circuit Television
'
CFR
- Code of Federal Regulations IFI
- Inspector Followup Item ISI
- Inservice Inspection LER
- Licensee Event Report
.
.
..... - -. -.
- -.
_,.
-
-...
.-
- - -,
.-
- - -..,
.
.
<
"
.
.o
g.
.
f-i
!
- Modification Approval Record
- Motor Control Center NCOR - Nonconforming Operation Report NOP
- Normal Operating Pressure NOT
- Normal Operating Temperature NQC
- Nuclear Quality Control NRC
- Nuclear Regulatory Commission NSSOD - Nuclear Shift Supervisor on Duty OSB
- Operator Study Book PM
- Preventive Maintenance RCA
- Radiation Control Area RCS
- Radiation Work Permit SLUR - Second Level Undervoltage Relays SP
- Surveillance Procedure L
- Senior Resident Inspector L
- Short Term Instruction
'
TS
- Technical Specification UE
- Unusual Event VIO
- Violation
l'
i l
,
l l
I i
I l
...
..
_._.
-......, _ _
,_.
. - _
_ _..