IR 05000416/1989025
| ML19332B843 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/03/1989 |
| From: | Rankin W, Sartor W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19332B842 | List: |
| References | |
| 50-416-89-25, NUDOCS 8911210012 | |
| Download: ML19332B843 (21) | |
Text
"
,
['
'
'
.
.,
,
- 'km *8,40'
k.
NUCLEAR RESULATORY COMMISSION
['
MEGION li j
101 MARIETTA STREET N.W.
g
, f ATLANT A, GEORGI A 30323
\\*****/
NOV 0 3 889 i
L.
'
!
l i
- .
Report No.: 50-416/89-25 i
,
i Licensee: System Energy Resources. Inc.
'
Jackson, MS 39205
D0;ket No.: 50-416 License No.:
HPF-29 t
Facility Name: Grand Gulf Inspection Conducted: Se tember 26-29, 1989 l
Inspector:
MM E ?--I dm
//-I* N y
U. Sartor, Jr.
Date Signed
,
Accompanying Personnel:
L. Cohen (NRR)
'
.B. Haagensen (PNL)
Approved by: M$ b-bi
//* I= f f i
W. H. Rankin Lhie P *~'
' Date Sigred
{
Emergency Preparx'ncss Section Emergency Preparedness and Radiological
L-Protection Branch
'
,'
Division of Radiation Safety and Safeguards i
Sli W RY
- '
Scope t-
[
.'
This routine, announced inspection was the observation ano evaluation of the
. annual entgency exercise.
Observations focused on selected staffing and
'
respante of the emergency organizations in the Control Room Technical Support Center (TSC), Operations Support Center (OSC), and Emergency Operations
-
Facility (EOF).
The inspection also included a review of the exercise
'
. objectives and scenario events, as well as observation of the licensee's critique to management.
l Results:
,
In the areas inspected, violations or deviations were not identified.
[
One exercise weakness was identified for the similarities with the scenarios for the dress rehearsal and evaluated exercise.
Within the scope of the exercise, as observed, the licensee fully demonstrated the capability of implementing its Emergency Plan and procedures to provide for the health and
'
,
safety of the public in a radiological emergency.
l t
0911210012 891103
'
{DR ADOCK 05000416 PDC
,
..
-
-
-
- - - -...
- -, -.
-
.
'
a
.
.
,,
.
t
,
.
i
,
REPORT DETAILS 1.
Persons Contacted
.
Licensee Employees
-
- W. Adcock, Manager Engineering Support
- D. Bottemiller, Simulator Instructor
'
- J. Cesare. Director, N1 clear Licensing f*W. Cottle, Vice President, Nuclear Operations
- C, Hayes, Quality Programs Supervisor
- T. Hildebrandt, Radiation Control Superintendent
'
- R. Hutchinson, General Plant Manager
-
- M. Kavanaugh, Senior Emergency Planner
- M. Larson, Senior Quality Assurance Representative f*F. Mangen. Director Plant Projects and Support f*C, Morgan, Manager. Emergency Preparedness
- R. Patterson, Technical Assistant General Manager
- J. Reaves, Manager, Quality System
- J. Robertson, Acting Manager, Nuclear Training
- L. Temple, Instrument ar.d Controls Superintendent
- M. Wright, Manager, Plant Support
.
- J. felverten, Manager, Operations
- G. Zinke, Plant Licensing Superintendent
Other lictnsee employees contacted during this inspection included engineers, operatern, mechanics, security force me.tbers, technicians, and administrative persornel.
'
Cther Organizations
- C, Caste, Florida her and Iight Cenpany
f *J. Kauffaen, NuTech NRC Resident Inspectors
- H. Christensen
- J. Mathis
- Attended exit interview (Attended meeting with management (Paragraph 2)
'
2.
Exercise Scenario (82302)
l l
The scenario for the emergency exercise was reviewed to determine that l
provisions had been made to test the integrated capability and a major portion of the basic clements existing within the licensee, state and local emergency plans and organization as required by 10 CFR 50.47(b)(14),
-10 CFR S0, Appendix E, paragraph IV.F. and specific criteria in NUREG-0654 Section II.N.
The scenario was reviewed in advance of the scheduled exercise date and discussed with licensee representatives at the final controller / evaluator meeting on September 26, 1989. Although no major problems were identified
_
and the scenario appeared adequate for this full scale exercise, a concern
--
..-
--
-
,
,,
'
_,. -
.
'
was later identified when the exercise scenario was compared against the dress rehearsal scenario that was conducted three weeks previously.
It was noted that both scenarios used the same initiating conditions for emergency classifications during the period of time when the Technical
'
Support Center (TSC) and Emergency Operations Facility (EOF) were
'
activated.
Specifically, the initiating condition for the Site Area
,
Emergency was a Reactor Core Isolation Cooling (RCIC) steam line break outside of containment which could not be isolated.
The initiating
.
condition for the General Emergency in both scenarios was reactor shutdown
and loss of decay heat removal capability and core damage predicted within j
several hours and subsequent containment failure.
Although different failures led to the condition of reactor water level decrease to below the top of active fuel (TAF) [ failure of residual heat removal (RHR) pump in the dress rehearsal scenario and failure of the operating control rod
!
drive (CRD) pump in the annual exercise], the emergency preparedness response by the TSC and the EOF was the same.
Additionally, both scenarios used the Standby Gas Treatment (SBGT) exhaust from the Auxiliary Building as the release pathway.
The similerities were discussed in a
'
separate meeting with licensee managemant personnel as indicated in Paragraph 1.
As a result of the conccrr.s expressed by the inspector, the
,
licensee indicated necassary corrective action would be taken to preclude
,
a recurrence.
The inspector idcatified the similarities of the two
scenarios as an exercise reakness.
Inspector followup will be tracked as
>
Inspector Followup Item (!FI) 50-416/89-25-01 to compare the 1990 dress rehearsal end annual exercise scenarios.
NJ violations or deviations were i&.ntified.
3.
Assignment of Resprnsibility (82301)
This area was cbserved to dutemine thct primary responsibilities for l
cmergency respunse by the licensee had been specifically established and i
I that adequete staff was available to respond to an emergency as required j
l by 10 CFR 50.47(b)(1), 10 CFR 50, Appendix E, paragraph IV.A. and specific
,
l criteria in 14UPEG-0654,Section II. A.
.
l The inspector observed that specific emergency assignments had been made for the licensee's emergency response organization and there was adequate i
staff available to respond to the simulated emergency.
The initial response organization was augmented by designated licensee representatives, however, due to the scenario conditions, long term or continuous staffing of the emergency response organization was not i
!-
demonstrated.
No violations or deviations were identified.
'
4.
Onsite Emergency Organization (82301)
The licensee's onsite emergency organization was observed to determine that the responsibilities for emergency response were unambiguously defined, that adequate staffing was provided to insure initial facility
-
_-.
-
.-
...
..
.
.
. - _..
d
.
s,
,
,
,
.
L
t accident response in key functional areas at all times, and that the
interfaces were specified as required by 10 CFR 50.47(b)(2),10 CFR 50, Appendix E, paragraph IV.A. and specific criteria in NUREG-0654,
.
Section II.B.
!
,
'
The inspector observed that the initial onsite emergency organization was
'
'
well defined and that adequate staff was available to fill key functional
>
positions within the emergency organization. Augmentation of the initial
'
emergency response organization was acconplished through mobilization of r
personnel assigned on call to the emergency organization.
The on duty
'
Shift Supervitor assumed the duties of Emergency Coordinator promptly upon the initiation of the simulated emergency and directed the response until
.
relieved by the Grand Gulf Nuclear Station General Manager.
No violations or deviations were identified, i
5.
Emergency Response Support and Resources (62301)
This area was observed to determine that arrangements for requesting and effectively using assistance resources had been made, that arrangements to accomodate State and local staff at the licensee's near-site EOF had been made, and that other organizations capable of augmenting)(the planned
"
response had been identified as required by 10 CFR 50.47(b 3), 10 CFR 50, Appendix E, paragraph IV.A. and specific criteria in NUREG-0654.
Section II.C.
State staff members for Mississippi and Louisiana were accomodated at the near-site Emergency Operations Facility.
Licensee cor. tact with offsite organizations was prompt and assistance resources from various agencies
',
were prepred to assist in the simulated emergency.
,
ho violations or deviations were identified.
6.
_EmergencyClassificationSystem(82301)
This area was observed to determine that a standard emergency clessification and action level (EAL) scheme was in use by the nuclear facility licensee as required by 10 CFR 50.47(b)(4), 10 CFR 50 Appendix E, paragraph IV.C. and specific criteria in NUREG-0054,Section II.D.
,
An emergency action level scheme was used to promptly identify and properly classify the emergency and escalate to more severe emergency classes as the simulated eniergency progressed.
Licensee actions in this
>
area were considered adequate.
No violations or deviations were identified.
7.
Notification Methods and Procedures (82301)
This area was observed to determine that procedures had been established for notification by the liransee of State and local response organizations
..
. -.
I
'
-
l-
,
!
.
g
.,
t
and emergency personnel; and that the content of initial and followup messages to response organizations had been established; and means to
'
provide early notification to the populace within the plume exposure
,
pathway had been established as required by 10 CFR 50.47(b)(5), 10 CFR 50, Appendix E, paragraph IV.D and specific criteria in NUREG-0654,Section II.E.
An inspector observed that notification methods and procedures had been j
established and were used to provide infomation concerning the simulated emergency conditions to Federal, State and local response organizations
'
and to alert the licensee's augmented emergency response organization.
No violations or deviations were identified.
8.
Emergency Comunications (82301)
!
,
This area was observed to determine that provisions existed for prompt I
as required by 10 CFR 50.47(b)(6)ganization and emergency comunications among principal response or 10 CFR 50 Appendix E, personnel
,
paragraph IV.E. and specific criteria in NUREG-0654,Section II.F.
Comunications among the licensee's emergency response facilities and emergency organizatf or, and between the licensee's unergency response nrganization and offsite authorities appeared adequate.
The licensee's critique identified som radio problems with the offsite monitoring teems.
. No violations or deviations were identified, 9.
Public Edecation and Information (82301)
-
This area was observed to determine that information concerning the
,
simulated emergency was made available for dissemination to the public as
>
l required by 10 CFR 50.47(b)(7),10 CFR 50, Appendix E, paragraph IV.D. and
'
I specific criteria in NUREG-0654,Section II.G.
Information was provided to the media and the public in advance of the exercise.
An Emergency News Media Center (ENMC) was established in Port
,
!
Gibson, Mississippi and appeared to be well equipped.
l l
No violations or deviations were identified.
,
Emergency Facilities and Equipment (82301)
!
10.
This area was observed to determine that adequate emergency facilities and
,
I equipment to support an emergency response were provided and maintained as I
required by 10 CFR 50.47(b)(8), 10 CFR 50 Appendix E, paragraph IV.E. and l-specific criteria in NUREG-0654,Section II.H.
The inspector observed the activation, staffing, and operation of the l
Control Room, TSC, Operations Support Center (050), and E0F. No equipment l-problems were identified.
l l
_
_
_
_
-
I
)
'
-
,.
'
.
,
i No violations or deviations were identified.
11. Protective Responses (82301)
I This area was observed to determine that guidelines for protective actions during the emergency, consistent with Federal guidance, were developed and
.
in place, and protective actions for emergency workers, including
!
,
evacuation ~ of nonessential personnel, were implenented promptly as
,
required by 10 CFR 50.47(b)(10), and specific criteria in NUREG-0654, Section ll.J.
An inspector verified the licensee had and used emergency procedures for formulating protective action reconsendations for offsite populations
,
within the 10 mile emergency planning zone (EPZ).
The licensee's protective action recomnendations were consistent with the Environmental i
Protection Agency (EPA) and other criteria and notifications were made to
'
.the appropriate State and local authorities within the 15-minute criteria.
,
An inspector observed that protective actions for onsito personnel within the protected area did not include an actual accountability. The licensee connitted to demonstrate this during their next annual exercise.
No violations or deviations were identified.
'
12. Radiological Exposure Control (82301)
This area was observed to determine that means for controlling radiological exposures, in an eirergency, were established and irrplemented
for emergency workers and that they included exposure guidelines consistant with EPA recommendations as required by 10 CFR 50.47(b)(11),
and specific criteria in NUREG-0654,Section II.K.
An inspector noted that radiological exposures were controlled throughout
!
the exercise by issuing emergency workers supplemental dosimeters and by periodic surveys in the emergency response facilities.
Exposure guidelines were in place for various categories of emergency actions and adequate protective clothing and respiratory protection were available and
,
used as appropriate.
'
No violations or deviations were identified.
13. Exercise Critique (82301)
[
L The licensee's critique of the emergency exercise was observed to L
determine that deficiencies identified as a result of the exercise and I
weaknesses noted in the licensee's emergency response organization were I
formally presented to licensee management for corrective actions as required by 10 CFR 50.47(b)(14),10 CFR 50, Appendix E. Paragraph IV.E.
I and specific criteria in NUREG-0654,Section II.N.
l
-
-
.
.
.
.
.
,
~
-
.,,
.
i
.
,
f
,
Player critiques were observed in the TSC and EOF immediately following i
exercise termination.
A fonnal critique of the emergency exercise was
held on September 29, 1989, with exercise controllers, key exercise
,
participants. licensee managemer.t. and NRC personnel attending.
The licensee's critique was adequate and discussed weaknesses identified as a result of the exercise.
Licensee actions on these weaknetses will be reviewed during subsequent inspections.
No violations or deviations were identified.
'
14.
Federal Evaluation Team Report i
The report by the Federal Evaluation Team (Regional Assistance Comittee and Federal Emergency Management Agency. Region IV and VI staff)
concerning the activities of offsite agencies during the exercise will be i
forwarded by separate correspondence.
15.
Exit Interview The inspection scope and findings were summarized on September 29. 1989, with those persons indicated in Paragraph 1 above.
The inspector described the areas inspected and discussed in detail the inspection findings listed below..
The licensee did not identify as proprietary 6ny
of the material provided to or reviewed by the inspector during this
'
inspection. Dissenting corivnents were not received froin the licensee.
.
it,9,m Nurrber Description and Reference 50-416/89-25-01 IFI:
The same EALs were used for the emergency classifications by the TSC and EOF in dress rehearsal and evaluated exercises (Paragraph 2).
i Attachment:
Scope and Objectives and Sequence
,
of Events l
l l
.
__
.
-
_ -. -
- - _.
.
_._
.. _.
-
..
-.- -_.
.
.
,,
.
.
e ORAND OULF NUCLEAR STATION 1989 EMERGENCY PREPAREDNESS EVALUATED REERCISE
2.0 SCOPE AND OBJECTIVES k
3.1 SCOPE The 1989 Grand Gulf Nuclear Station Emergency Preparedness Exercise, to be conducted on September
!
27,1989, will test and provide the opportunity to
'
evaluate GGNS's Emergency Plan and Procedures.
It will also test the emergency response organization's ability to assess and respond to emergency conditions and
,
'
coordinate efforts with other agencies for protection
,
.
of the health and safety of the public.
l
'
The scenario will depict a simulated sequence of events, resulting in sufficiently degraded conditions
t to warrant the mobilization of GGNS,. State and local agencies to respond to the emergency.
The Evaluated l
Exercise will have full participation by the GGNS omergency responsa organization, and State of Mississippi, Claiborne County, and Tensas Parish, and i
partial participation by the state of Louisiana
.
Whenever practical, the exercise will incorporate provisions for
" free play" on the part of the
,
participants.
l
!
2.2 OBJECTIVES
,
The Grand Gulf Nuclear Station 1989 Emergency l
Preparedness Exercise objectives are based on the
!
Nuclear Regulatory Commission (NRC)
requirements
,
delineated in 10 CFR 50.47 and 10 CFR 50, Appendix E.
,
Additional guidance is provided in NUREG 0654, FEMA-REP-1, Revision 1.
.
The major objective of the exercise is to evaluate the integrated capability of a major portion of the basic
elements existing within the onsite emergency plan and emergency response organization.
The specific i
i objectives of the exercise to be demonstrated are (
listed below.
o Denonstrate emergency response integrated
,
capabilities by activating the emergency
-
organization and staffing the GGNS Emergency l
I (
2-1
,
.
,.. _ _ _.
.
.. _ _. _.. _.,..., _.., _, _.. _.,.. _ _.
_,. _. _. _.. _.., _,.
._,.,___m._,.. _.. _. _ _., _.
. _, _... _ _ _ _
_ _ _
.
_
_ _ _ _. _
-
_ _ _. _.__
.
_ _
.
!
j
-
!.
,
,
t
'4
B
!
'
o
!
'
,
I l
GRAND GULF NUCLEAR STATION l
1989 EMERGENCY PREPAREDNESS EVALUATED EXERCISE Response Facilities (ERF's), including the control Room, Technical Support Center, operations Support Center, and the Emergency Operations Facility, Emergency News Media Center, the Corporate Emergency Center, and the
-
Emergency Information Center and by
implementing access control to these
.
facilities.
j
'
'
-'
.-
o Demonstrate the adequacy of ERF's and their personnel, documents, and equipment to support, direct, and control emergency operations.
,
Demonstrate the reliability and effective use of o
onsite and offsite emergency communications equipment and procedures.
o Demonstrate the ability of appropriate
individuals to direct the required emergency
!
organizations and maintain continuity in the
!
'
implementation of the Emergency Plan using the Emergency Plan Procedures and the Corporate Emergency Plan Procedures.
,
o Demonstrate the ability of the emergency organization to assess the initiating conditions
>
for determining which emergency action level has
-
been reached and properly classifying the accident.
Demonstrate the ability to recognize more o
severe accident conditions and escalation of emergency classifications.
,
o Demonstrate the ability to perform dose calculations utilizing radiological and meteorological information to determine the magnitude of and for continuously assessing the impact of the release of radioactive materials to the environment and make the appropriate recommendations for of fsite protective actions utilizing all relevant factors.
'~7
.
-.
..
.
---.. _ _
. -
.
.
._.
i
-
-
..
I
'
.
i
!
'
,
!
,
GRAND GULF NUCLEAR STATION l
1989 EMERGENCY PREPAREDNESS EVALUATED EXERCISE
.i o
Demonstrate the ability of offsite field monitoring teams to use emergency equipment in performing radiological surveys.
'
o Demonstrate the appropriate equipment and procedures for determining onsite radiation levels.
o Demonstrate the ability to perform search and j
..,.
rescue, as required.
,
o Demonstrate Medical Team Response and
Transportation for a simulated contaminated
.
injured individual.
o Demonstrate the ability of the GGNS emergency organization to provide the Emergency News Media Center with accurate and timely
information so reports may be made to the news media.
2.3 SIMULATIONS Decontaminationrof onsite energency workers and o
equipment will be simulated.
a o
Anti-contamination clothing will be worn, as
'
deemed necessary by players, in response to simulated scenario conditions t however SCBAs will be carried and D21 worn.
Repair activities will be simulated.
o
.
o Recovery actions will be limited to planning l
discussions.
,
o Protected Area and Controlled Area Evacuations E
will be simulated,
'
Actual plant coolant and containment Atmosphere o
samples will n21 be drawn.
.
2-3
_ _..
_
-
-
. -..
-
-. -. - - -
-
_ _ _ _
_ _ _
__ _ _ _ _ _
_
_. _
._.
_ _ _ _ _ _.
.
_
.__
. _ _ _ _..
_ _ -.
_
i
..
,
,
'
.
.
e GRAND GULF NUCLEAR STATION a.
1989 ENERGENCY PREPAREDNESS EVALUATED EEERCISE i
o Use of the Backup EOF and ENMC will D91 be demonstrated, i
o Performance of offsite radiological monitoring
from aircraft or water will D91 be i
demonstrated.
.
o Shift staffing for long-term operations will D91 be demonstrated.
.,-
o Due to plant operational requirements, there l
-
are a limited number of OSC participants.
Therefore, some non-critical OSC Teams may be i
simulated at the discretion of the Lead OSC
,
Controller.
Given the 3imited number of OSC participants, restocking of OSC supplies (e.g.
,
SCBA Bottles, PC's, Respirators, etc.) will not
be demonstrated.
Note:
Amp 2e supplies are available in the event of an emergency.
'
i 2.4 LOCAL AND STATE GOVERNMENT OBJECTIVE 8 e
The Grand Gulf Nuclear Station 1989 Emergency Preparedness Exercise objectives for the State and Local agencies are ba'ted on the Federal Emergency
[
Management Agency (FEMA) requirements delineated in
l NUREG-0654, FEMA-REP-1, Rev.
1, Guidance Memorandum
-
Ex-3, March 1988 and MS-1, November 1986. The specific objectives of the exercise to be demonstrated by the l
State and Local agencies have been sent under separate
cover to the respective FEMA Regions.
l
'
.
I
e
,
l t
l 2-4 L
L
.
.. _..
.. _ _ _ -
.
.
.
.
.
...
..
..
.. n 4)
.
..
'
.
e o.
,
Actual scenario summary
-
'
Time Time Exercise is terminated.
'..
.
.
i
$
b i
s a
b
1 h
(
7-7
.
-
.
..
..--.
_
_. __
__
_. _. _
_
_
_ _ _
,
l l
.,
j
..
i
,
o GRAND GULF 1989 EVATUATED RYERCISE EVAIAJATED EXERCISE SCENARIO SEQUENCE OF EVENTS Actual Scenario Summary Time Time
'
,
0700-00/30 INITIAL CONDITIONS Grand Gulf Unit 1 is operating i
at 100% power for 300 full power days, following a
routine refueling outage.
GGNS did, l
.
however',
experience problems with condenser circulating water i
-
'
l in-leakage, so the condenser
'
waterboxes have been entered recently (within the last two weeks) for leak detection and
,
l condenser tube plugging.
Unit 2 remains under construction.
[
The HPCS pump is out of service i
due to a severe bearing problem causing excessive vibration.
HPCS in torn down to allow i
-
'
bearing replacement.
A 14-day LCO has been in effect since
,
noon yesterday.
Repairs will take at least two more days.
- '
A reactor coolant leak rate test
-
is in progress to determine
whether an existing
gpm unidentified leak has worsened.
- The
"B" CRD pump is out of I
servics for pump seal
,
replacement.
It is expected to
-
be repaired within 4 days.
The "A" SLC pump is inoperabla
due to failed heat tracing at
,
the pump suction.
"A" SLC is tagged out and its piping is opened to remove solidified sodium pentaborate. The "B" SLC pump is operable.
7-1 i
l
l
-
.--.. -.
.
.
...
..
.
..
..
...
.
.
.
.
.
...
..
....
-
-
.
.. ~.
.- -
-. - - -.
.
-..-
_ _ -
._ _ _
!
^
..
!
.
.
!
.-
.
Actual Scenario Summary Time Time f
.
The site ambulance is in Vicksburg for replacement of a i
blown engine.
It is expected
.
to be ret'.srned to the site l
within three days.
- The grid is unstable due to
'
unusually high demand caused by a
heat wave, coupled with
unexpected forced outages at
,
.. .
Waterford 3 and ANO-1. The load l
dispatcher has requested that
.
'
,
Grand Gulf provide full power l
to the grid to avoid industrial
.
l load shedding.
- LER 87-235-20, which describes
~
l-
,
the failure of the SRV l
electrical function at the (
Brunswick Steam Electric Plant
'
(BSEP), has been forwarded to
-
all licensees for review.
.
j regardless of the type of valves t
-
installed in the plant. The LER describes a condition caused by l
the hardening of LOCTITE sealer j
around the actuating solenoids,
..
which prevents electrical s
functioning.of the SRVs, while l
allowing the mechanical function i
'
to remain operable.
GGNS management has decided to continue full power. operation while engineering investigates
.
!
this issue.
Management has
,
directed that no SRV. testing be performed until engineering has
]
completed its investigation.
0730 00/00 Initial conditions are established.
Commence Grand Gulf 1989 Evaluated I-Exercise.
!.'-
,
0740 00/10
'A minor fire is reported in the oil storage locker of the Turbine Building 93 ' elevation. Offsite fire
]
fighting assistance is not required.
,
7-2
-
. - -..
.. -... - - - -. -.. -.. - -. - -. - - _ -. - _ -.. -. - - - - - -.. -.,. - _. _. -
..
_
. _ _
. _. _
_ _. - _ _ _ _
-
i
'
!
-
l l
.
'
!
!
Actual Scenario Summary
.'
Time Time
i 0748 00/18 The fire is extinguished by the Fire
.
Brigada.
'
0800 00/30 Control Room indications show that RCS unidentified leakage has
-)
increased to greater than 50 gpm.
A controlled shutdown may be
,
commenced.
f An ALERT should be declared per 10-
ALERT
S-01-1, page 3, No.
2.2,
" Abnormal i
.
Primary Leak Rate, Coolant leak rate
[
greater than 50 gpa."
r 0815 00/45 The RCS leak rate is stable at 55 gpm.
Shutdown is continuing.
0900 01/30 Debris inadvertently left in the l
condenser from the recent condenser tube plugging job breaks loose and partially clogs the suction piping for the condensate pumps.
This
!
'
causes the condensate pumps to have i
reduced flow and discharge pressure and results in low suction trips of
,
all the running feedwater pumps and
a" complete loss of feedwater.
i This total loss of feedwater results i
in a reactor scram and recirculation pumps trip.
Level drops rapidly to below the HPCS/RCIC initiation setpoint.
'
'
,
The HPCS system is out of service; and though the RCIC system automatically starts, the pump does not deliver rated flow due to a
malfunctioning governor valve.
Containment isolation in response to this event is successful.
This isolates the unidentified leakage to the drywell from the drywell chilled water system if not previously accomplished by operators via 7-3
-
.
__
_
~..
.
.
.
..
.
..
.
.
-
_ _ _.
.. _.. _.. _..
.,._
... _ _ _ _. _. _
__
__
_
_
..
'
,.
,
,
~'
.
\\
.
i
!
e
,
Actual scenario summary i
Time Time i
.
!
.
"freeplay".
The MSIVs close and tho l
i EDGs start as RWL drops below
-
150.3", and then begins to recover.
i
+
SBGT automatically starts.
'
LPCI/L'CS pua@s automatically start e
and run on minimum flow. The reactor is stable but pressure remains high.
>
0920 01/50 An operations / maintenance team
.
checking the RCIC turbine governor
[
,
'
.-
'
finds that the governor will have to be replaced.
,
!
0925 01/55 The operations / maintenance team in
!
the RCIC equipment area checking the
turbine governor observe steam leaking through a
crack in the l
upstream pipe to valve body weld on
)
E51-F045.
The crack is beginning to
!
worsen and a
large puddle is i
beginning to form.
l
,
0930 02/00 The RCIC turbine steam supply line crack widens rapidly.
All personnel move to rapidly exit the arent h6 wever, a technician trips and falls in the puddle.
(DAMAGE TO INDIVIDUAL
}
DESCRIPTION 1ATER)
A short time later,it is determined that the injured individual is
'
contaminated and does require transport to offsite medical facilities.
Annunciators are received in the CR indicating that the RCIC has experienced a pipe rupture in the
RCIC room.
RCIC fails to isolate.
Reactor water level begins to drop slowly as only CRD pump
"A" is providing makeup to the reactor.
A radioactive release to the environment begins via SbGT exhaust.
7-4
. --
.. -
.-
-. -
-. ~. ~. -
-. -. - -.
.. -
.- -....
.. -
.
,
i
'
-
.
.
.
{
.
l
!
l Actual Scenario Summary
-
Time Time
i
'
SITE AREA EMERGENCY A SITE AREA EMERGENCY should be
!
declared per 10-S-01-1, page 8, No.
l 5.4,
" Steam Leaks, RCIC steam line break outside the containment which
!
cannot be igg M ad".
j 1005 02/35 Any attempts to depressurine the
!
reactor using ADS are unsuccesatul
..
,
due to " frozen" solenoids on the SRVs l
due to excess sealant that has l
'
'
solidified, the safety valve function
'
of the SRVs remains operable (SRVs will lift due to excess pressure if encountered).
Attempts to re-open
'
MSIVs and dump steam to the condenser
,
also fail due to mechanical binding
!
!
of.the inboard MSIVs.
Reactor let 31 drops slowly with I
reactor pressere dropping, but
,
remaining higher than LPCI/LPCS pump
shut of f head. Swell of the incoming cold water eventually stabilizes and then slowly raises reactor water
>
level.
1100 03/30 The operating CRD pump fails.
f Reactor water level begins to lower.
1115 03/45 Reactor level has dropped to the top
,
of active fuel (TAF), with pressure
!
remaining far above RMR/LPCS capability.
The steam release
,
continues.
j GENERAL EMERGENCY A
GENERAL EMERGENCY should be I
declared per 10-S-01-1, page 17, No.
12.5,
" Plant Shutdown Function, Reactor shutdown and Loss of decay
'
heat removal capability and ggEE DAMAGE Dredicted within several hours And Subsequent Containment Failure."
1115 03/45 The Auxiliary Building RCIC Area ARM begins to show elevated radiation levels and the SBGT Exhaust Monitors 7-5
.
.
.
.
..
.
.
.
..
.
. _ _ _. _ _ _, _ _ _ _ _ _ _ _ _ _ _ _ - _ _. _. _ _ _
-
.
-
.- -
.. -
-
. _
_ _ _ _ _ -- -.
.
-.
,
l
'
-
.,
-
i
,
.
-
+
Actual scenario Summary
]
Time Time
B r
-
,
'
show that a significant radioactive release is in progress.
Reactor i
pressure remains in excess of the low
'
pressure ECCS shut off head.
j 3215 04/45 Reactor level has dropped to -245.
i LPCS begins to inject as reactor
!
pressure has decreased to below LPCS l
nhut off head.
fevere clad damage
!
has occurrred.
RHR begins to inject
!
...
a short time latur.
!
1230 05/00 The core has been re-flooded.
The release continues as operators
,
attempt to depressurize the reactor.
Reactor pressure drops below the
,
shutdown cooling permissive.
j
<
1240 05/10 Shutdown cooling is placed in
service.
i
'
l Repair teams successfully isolate
!
l RCIC by closing the inboard l
steamline isolation valve.
The
'
release is terminated.
l
[
Anstorm is brewing in the vicinity
of GGNS and meteorological conditions
change rapidly.
l 1300 05/30 The plume is dispersed out of the 10 h
mile EPZ by high winds.
The reactor is placed in cold shutdown condition.
i Downgrade discussionn are in
,
.
progress.
1345 06/15 offsite doses are returned to
background.
A Recovery organization is established.
.
Recovery planning is initiated, with
long term organization and response plans formulated.
1430 07/00 The 1989 Grand Gulf Evaluated
.
l
' -
7-6
.
.. _. - _
_
__
,. _.., _., _ _.. _ _ _ _, _ _ - _ _, _ _ _ _ _. _. _ _ _ _. _ _ _
__
-. -__
.... _. - _ _ _ _. _ _ _ _ _ _ _ _
_
_
_
.
.
.
,
U S. NUCtLAR MEGULATORY COMMi$$lON
<*.6**
'oa se*'s i.-=spe.w.n r
'
en,,t,,0 3 701 Od WP/T A b t t
e
-
,
,
INSPECTOR'S REPORT
'
'
e4.C Okl4
,,,h.,,,.. n /f ;
y)
'
Of fice of Inspection and Enforcorrent
'
S{h RT O R w/.
.
(Ahen L { /Ver
.PZTB)
" " ' " ' "
'
'
'
Skneeoc s c,,'T'% ICen le ck)
e
.g.p.t
%t a t i% 5.IC D. 74 siCt%5tlb4DO.
""g,",[
Doca st %D. 0DsCf u13.gis'
g e,is c. tigggst 40 0 h0 500
.0
,.
' *
'
f"i"A w (f O M3
4/ / h I
$$ Zlg a
. -.00 8, (-
[, o
- '*
D. Dikt'l l
l l f f
~
C
...t.L.Ct
-- -.--}
..
............., _ -,. <, _
...., <, _,........
_____
"
'
50.
l
,d t..qc chs s pf ertt $1.ps
,
ginkE '
s,e
,*:
,
>
w
...,..
-
-
,.
... _.......
l19 A i9 8-"o**'"#'"**'"'"
'2 4-
/
6l9 2j Of[']. Qar.v: cx.m ~;wnip p m ;,6
.m.:n,,,p~J.
g
'
t
.
,
-.r.sj
- ,;,,,,.a c,.
,,, m.e... w.c o m.
.
,,
J2. S.s(Y, m.
4.? vilif tJ..L.h f 6(C
].4. % Osie.,
'
i,........'I
- '8** *
_
,
.. _,,,
,,.., <..
,,.......
,.. -...., _
.
.
_
_
_
].nc,e asoreiens i.
a. se.ci.ii i a
- i%oo.
is-s +.ist ei.o.,
..g..,
u ' - ' "'
>..o,
,
,
l t*'QLvXQ m *w.m a -
M M..*e.:ts.t o n
'
- -
,, ygg,,,,
= = ':* a.i,* 'jo ""~ a
" T,'j,;,',';,,"*
I arnm neo"t
]
'
a
.. a. 4. A.
-
,
c e" *'*5 xL
.o
..c c,.
..,,,,,,
.,....
arn...
.
.......
uao
.cv.
-
,,,,,c,,,
.......
.j.!c
,
.i.n
.
.i.n ni i., n., i. 3.. n., i.. i
.. va.,m a cu.to n.o;, ;,
- j
.....
( i ; i,...
,
umsmwe m ann usm e ss
. _,,, <..., _
. _,,...., _
. _.... _. i
. _..... _ _ m
. _ _...,.
,
n!,
!
ie t
{il,,s,t ns
. _, _......
ie
.i.
o = s.,t
.,.
,.
.:.
,.
n.
.
s
, n
..-
.
.
.
.
.
.
-
w!!!I !ki i l il ll E
, n
.
.
,!.! ! ! !!
l l.
4 E l 1 il ll i S
-
,
.
.
i l,1
! If E WI !!!!I
.
.
.
.
..
i l e
!
i,
i, i,
, i,iil m, i
,i,ii
.
,
i i i
nonoai
.
'
-
,,
.
,
Iiill l
iliiI
'
'
i i ii
,
ii
, i liill
,liil l
=
i i
,,
i ii i,
ii,1I iliil o
i i
,,
,
,,
,,
liill d>,8 iCO C iliil liil e
i 5 A211#i l
'
l
.
i i
i i e i i
'
Ii,Il
,
'
iliil a
'
i i
,,
i i,
i,
1,,il ili,1
=
i i
,,
,
.
ii i,
i.,il
,l..I
>
=
,,
,,
i
,
,,
,,
IiiiI
.
i s M N o ll ir a I,o in c iliiI I,i1
'
-
.
i i
, i i i i
i Iiil}
iliil i i i i i
'
ii
, i
,
iliil I,ill l
-
, i i i i
ii
, i I,,il i
I,il o
ii
,,
,
i,
i,
i I i i ll liiI iIiil liiI
'
i i i i i
^
e i
i ii i i v i i
liill i
liil
-
'
i i i,
i ii i,
,
Iiil I,it]
'
'
i i i i i
i,
,,
,
i,,i o = =re....
>
>
, C,
'
,
,,
,,
,
,
l they""? ~'_.. *
.*.3
',*. 3,, 2..*,1LO 4: d + lL1MM $3
-
._
..
- _ _ _._ -, -
.- - -,
--
-.
-
. - -
-
-. -.
__
- _. _. _.. _ _ _ _
---._._______.___w_
_ _. _
,
'
'
x
"
.
_
.
.
,
"""
' L t
-.
-
-
,,
-
w g
',,.
g
"
w i _l El s i
,_,,
,
_
_
y,
-
E l
-
- y
-
-
-
d s i s :
'
B e_ r_
e y
-
- -
--
E E
<
,
E g
-
-
-
a
_
t-
?
e
-
l p m
-
-
-
l
-
.m
y
--
-
.-
=
-
,,l
-
.
!
T.
TX.
> llb
--
3-g -s
>
j
..=
..._
-
gl
.-
o,
%
p-V W w
<
m m._
w m-
]
T' W W
"-
-
p
- -
p g 7)
- l
,
M
- W h. _
if n
.
-
._.
m _
__
,
-
=
- _ -.. -.
.
_
~d" 9g y)
8l
..
-
-
-
-
-
-
_tu g
..
m
-
t _ _ _
_
.._-
c
<
p:
-
M
-
N T
-
s
<
.c L,
$ ~t.
E W G
$
E
$
E
.' ~l
-
.
.
~
~
-
!
~
-
<
.;
y y
--
-
.
g*
k
-
-
W C '-b
.
'
-
-
-
i
.9-it k
-
-
j
-
-
-
m v
-
m m
g g g -T k
W g
g
,
-
-
.
1 -
E f
-
}
~
s a g p t o E
-
-
_
a i.
3: C e
h d (2
-
i
,s r
-
-
r.,
---
(R. )v
!
!
-y
_.
-
_
I b
11.
O h
L
_
_
w tw g
-
\\D C 4 g
$
I.
c %
-
-
,
ll g
e u e
-
-
-
o h J
.
_
R
',
o
,
.>
i V) x
p t
a j
@ W I
g-aa*
l %
-
l
,
g ette J
-
d
! EEEE s
s g
i n t a 9 i
s a
>
z e
_
\\.o % '2 e
u
-
s
a yt w
c et
-
g to
-
'
-~m.
s I--J
-~m
.
~m,
N C 22 2 c
& me cc c e ce c c h
EB B B BE E E
'E E E E u e g __
,
.
-+-,-we-ww-w-w-r-----ww
-~sa v
,w
.. - - - - - - - - - - - - - -
- - -
-
- - - - -
-.
. _, _ _ _ _ _ _ _
.. -
AUG 2 3 C5 "
i
.
..
'~
!
,a
!
,
ENCLOSURE 6
!
'
!
gniultant/ContractorDataforInsoections/ Reviews
' For Fee Period:
$ph M,
f
>
,
t
}
-
'"
Faciltty:,L1i W o
\\Mu;7 f
'
Docket (s)/ Report (s):,87} W4 /8 9-2 61
,
-
I r
I
i'
-
Dates of Inspection:
6@ 2. 6 - 2 } '
i 3, M444 A q h
Names of Consultants / Contractors:
O t
.
!
!
i
-
,
O Nueer of Hours per Contractor:
l
- Purpcse of Consultant / Contractor:
'
t
_
h
t l'
I
!
'
,
.
- Indicate whether consultant / contractor was used for inspection, type of
..
inspection or whether it was re, view work and type of review.
[
~~
Signature:
/O/2.3/N Date:
/
/
/
i
I
_ _ _
_
. _ -
__
.
. -. -
.
.
.
.
.
..
.
.
..