IR 05000286/1981001
| ML19350E076 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 05/22/1981 |
| From: | Kenny T, Kister H, Rebelowski P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19350E071 | List: |
| References | |
| 50-286-81-01, 50-286-81-1, NUDOCS 8106160375 | |
| Download: ML19350E076 (14) | |
Text
'~
.
,
'.-[.
DCS No. 50286-810131
'
,
(
v
.
.
U.S. NUCLEAR REGULATORY COMMISSION
'
OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-286/81-01 i
Docket No. 50-286 t
Licensa No. CPR-64 Priority
_
Category C
!
--
Licensee:
Power Authority of the State of New York 10 Colursus Circle New York, New York 10019
.
i
'
Facility Name:
Indian Point Nuclear Generating Station, Unit 3
k Inspection at:
Buchanan, New York Inspection conducted:
January 1,1981 to Feeruary 28, 1981 Inspectors:
( I,p2 M
-
- 2.- M
!
.
Receiowsy(J5enior pesicent Inspector cyte signed I.
( \\ fly.i 1.A D
')- p V/
i.
nny, nesjt y t in ec.or este signec/
,
ca:e signed
-
Apprqved by:
W V
_
(
ft ca:e sigtfed '
H. KI) ster, ActYng(JChie(f,IndianPoint i
Resident Section Inscection Summary:
Inspections on January 1 to February 28,1981 (Recort No. 50-286/81-01)
Areas Inspected: Routine onsite and regular and backshif t Inspections of plant operations including shift logs and records; obsersation of physical security; review of monthly and periodic reports; plant tours; Risk Assess-ment Meeting; damaged low pressure turbine; service water con _tainment in-t spection; review of service water motor cooler return lines, Lessons Learned
!
(precompliance review); surveillance test observations, Ion Track Instrument review and Congressional staff members visit.
The inspection involved 112
inspector-hours by the resident inspectors.
Results: No items of noncompliance were identified.
l l
t
.
!
Region I Form 12
'
(Rev. April 77)
810616e875
.
,
p..
-
. _ -.
.
. -. -
.-..
-
-
.
.
.-
,
,
,
OETAILS
,,,
1.
-Persons Contacted M.
Albright, Instrument and Control Superintendent J.
Brons, Resident Manager C.
Connell, Reliability and Performance Supervisor
3.
Dube, Security and Safety Supervisor W.
Hamlin, Assistant to the Resident Manager W.
Josiger, Superintendent of Power-J.
Kelly, Radiological and Environmental Services Superintendent J.
Vignola, Maintenance Superintendent S.
Zulla, Resident Manager S.
Muno:, Technical Services Supervisor The inspector also interviewed and observed other licensee employees including members of the operations, health phycies, technical services, maintenance, and security staffs.
2.
Review of Plant Coerations a.
Shift Locs and Oceratine Records The inspector reviewed the following logs and records on a sampling basis for the period of thie eport.
Senio: Reactor Cperator Log
--
Co'; Shutdown Log Sheets
--
--
Jumper Log
--
Running Equipment Log Sheets
--
Reactor Coolant Leakage Surveillance Sheets
--
High Radiation Area Locked Gate Lists
--
Control Room Log Sheets
--
Conventional Area Log Sheets
--
Nuclear Area Log Sheets
--
!
.
'
.,
9 e.,
_._.._
_.. _.
_
.
.
.
.
.
.
Shift logs and operating records were reviewed to verify _ that:
Control Rocm log sheet entries are filled out and initialed;
--
Auxiliary log sheets are filled out and initialed;
--
Log book reviews are being conducted by the staff;
--
Operating orders do not conflict with Technical Specification
--
requirements; Incident reports detail no violation of Technical Specification
--
LCO or reporting requirements.
Acceptance criteria for the above review included inspector
,
judgement and requirements of applicable Technical Specifications and the.following licensee procedures:
AP-19, Surveillance Test Program
--
AP-13, Jumper Control
--
AP-10, Work Permits, Raciation Exposure Authori:ation,
--
Operating Orders AP-21.4, Log keeping
--
The inspector had the following comments relative to the records reviewed:
.-
The control room logs appear to contain minimal information on status of ongoing operations. Examples of items not included in Control Room logs ~and appearing as " Pass-a-long" notes were:
Status of charging pump which was out of service
--
Accumulator status changes
--
.
Battery voltage switch not operable
--
Safety Injection Pump out of service
.
--
- 33 Diesal Generator Pre-lube puma locked out
--
These items were discussed with the Operations Superintendent for review and actions. This item remains unresolved pending licensee's action. (50-236/81-01-01)
The inspector had no further questions relativ'e to records at::
legs.
b.
Plant Tour
.
.. - -.. -.
.
. -. - -.
-.
-.
7-
.
.
..
.
,
During the course of the inspection, including backshifts, the inspector made observations and conducted tours of:
Control Room
-
--
Auxiliary Feed Water Building
--
l
!
Yard Area and Perimeter
--
Rad Waste Building
--
Turbine Building
--
Security Control Building
--
.
'
Primary Auxiliary Building
--
Containment Building
--
.
'
Emergency Control Center
--
Diesel Generator Building
--
Intake Structure
--
The following determinations were made:
i (1) The general plant / equipment conditions were checked to insure operability and verification of standby equipment.
Equipment was checked for leaks, piping vibrations, pipe
--
hanger / seismic restraint settings, oil leaks, instrumentation functioning, and recorder functioning.
(2) Maintenance requests have been initiated for equipment in need of maintenance and that the proper priorities are being
,
given to effect the needed repairs.
(3) Plant areas (to include cabinet interiors) have been checked for fire hazards. Fire alarms, extinguishing equipment, actuating controls, firefighting equipment and emergency equipment have been checked for operability.
(4)
Ignition sources and flammable materials were being controlled in accordance with licensee's procedures.
(5) Activities in progress were being conducted in accordance with licensee's administrative controls and approved procedures
and that these activities do not interfers or have the potential to interfere with the safe operation of the facility.
.
u k
,
-,.
--.
,,
,
~
- :
=-
-
-.
-
-
.a
...a
.
-.
~
.
-.
,.
.
,.
-. - - o
.
.
,
'
(6) Interior of selected electrical and_ control panels (including control room panels) were clean, free of debris and do not contain unauthorized jumpers or bypasses.
(7) Radiation protection control. were properly established by
'the fact that:
areas were posted as required by 10 CFR 20 and 19;
--
periodic measurements of radiation levels were made by
--
the inspector;-
REA requirements were being followed and the requirements
--
appear appropriate for the job or activity; licensee's procedures were being followed;
.
--
step-off pads were being properly maintained and that
--
contaminated clothing or debris were being properly collected and disposed of.
(8) Plant housekeeping conditions / cleanliness was being maintained.
During a normal plant tour of the 15' elevation in the Control Building,
..he inspector noted on the service water local remote control board at the 15' Primary Auxiliary Building level that the actuating handles on five of nine service water pumps were missing. The switch handles in-place could be used to position the pumps with missing handles.
This was reported immediately to the Operations Superintendent who said that the switches had been removed for modifications to satisfy
--
previous human factor analysis. A review of licensee's PEP-RPC-2, Rev. 1, " Control Room Inaccessibility *, requires the shutdown of service water pumps at the -local control board if required. The licensee acknowledged that hand switches should have been modified one at a time. The Maintenance Work Request used to change over other recommended switch modifications will reflect this criteria.
Th!s item is resolved.
3.
Risk Assessment Meeting-NRR Cn February 4,1981,'the inspector attended a meeting of the Zion-
-Indian Point (ZIP) licensees regarding the risk assessment analysis.
The licensees presented additional information on the mitigation of incidents at these respective sites. No fixed date for the results of tneir studies or actions planned where presented.
Tentative dates for full reports were discussed and further information was requested. Later information received by NRR indicated that the -
licensees will submit an 8,000 to 10,000 page report on their studies
. in June'1981.> Hardware changes or modifications have not been identified to NRR as iof date of this report.
.
.
s,
-.-.
.... - - -
,
.-
-.
.
.
-
,
6
-
An outline of the Report was presented and consisted of:
Preface: " Road map" and users guide
--
Contents
--
Executive Summary: 20 to 50 pages
.
--
r Summary Report:
200 to 300 pages summarizing main report (no
--
new information)
Main Report
--
Contents
,
Introduction / Summary Module Area
!
Section 0, Methodology
--
Sectin 1, Plant Analyses
--
Section 2, Containment Event Tree
--
.
Section 3, Phenomenology
--
Section 4, Transient Analyses
--
Section 5, Source Terms
--
--
5ection 6, Consequence Analyses t
--
Section i External Events
'
"
--
-
, Section 8, Integration
-
,
Section 9, New Features
--
i Present schedule for publication was determined after the meeting to L
be late June. The inspector has no further questions at this time.
4.
Damaced Low pressu"e Turbine
>
On January 31, 1981 at approximately 6:15 a.m. the licensee experienced a high vibration alarm on No. 4 Main Turbine Shaft bearing. Bearing is at south end of No. 31 Low Pressure Turbine, (between No. 31 and
,
No. 32 Low Pressure Turbine (LPT)). A reading of 9, mils was recorded.
'
Immediately after the vibration alarm, chloride alarms on the condenser peaked.
Immediate load shedding was instituted and Emergency Notification a
r e
" L._. a
, T -._ _
.
.,
. _. _
_._
.
._
_
._
.
,
-
.
1-
-
-
.
-
-o
System was used to notify NRC of the reduction in power. Condensers were alternately isolated to identify the source of leakage.
At 8:15 a.m.~ a shutdown to hot. shutdown condition was ordered. At 3:39 4.m. a reactor trip-occurred as a. result of No. 31 Steam Generator High Level. The reactor was it approximately 9% power with one Main Boiler Feed Pump supplying he steam generators.
No engineered safeguard system initiation was required or started. At the time of the trio the unit was stable and normal cooldown at approximately 30 degrees F/ Hour was in progress. The licensee assumed a failed blade on No. 31 L.P.T. ~ Verification of turbine damage was made et approximately 3:30 -
p.m. when er.try was made to the steam side of the condenser.
The licensee notsd sheared blades in the "L" row blading.
The cause of the failure is being investigated.
The unit proceeded to cold shutdcwn to perform turbine repairs.
The following operating data was obtained:
7, Load Reduction Chloride Intrusion to Steam Generator Time power 3 team Gt,. No.
Test Results in oom at:
0600 375 7:30 a.m.
3:15 a.m.
11:30 a.m.
0630 800
205 335 239 0700 200
220 333 193 0730 120
235 324 206
--
0800
.115
250 359 20E 0840 Offline Steam Generator Levels at Time of Trio Off charts
75% (Program level)
SC%
50%
42%
.
.
! -
..
x.-
.
...
-
.-
-.
,-
-. ---~~~
~-
-
.
.
.
.
.
A V
g
.The details of the licensee': inspections and repairs are noted in the Nuclear Safety Evaluation 81-03-022 TURSINE, Rev. O which describes the incident.
In summary, the inspecticn of the LPT #1 found that the L-1 generator end lost a blade which severed numerous condenser tubes. The problem was attributed to excessive hardness in the affected turbine blades and required replacement of all L-0 group generator end, and 6 blade groups in L-1 generator end, and L-2 governor end.
The other LPT units were also exa=ined and single groups of No. 2 LPT and two blades of No. 3 LPT were replaced.
.
The steam generators were drained and flushed and condenser repairs were performed, however,- unit repairs were still underway at end of the report period. The inspector had no further questions regarding
,
the turbine repairs.
5.
Inscection for Service Water Leaks in the Containment The licensee's procedure 3PT-BW3 requires that at intervals no greater than 14 days, whenever the reactor coolant system is above cold shut-down, a visual inspection inside the containment building shall be performed for identification of service water or other liquid leakage.
On January 25, 1931 at 10:00 a.m., while the unit was at approximately 850 MW, the inspector accomoanied the Operations Superintendent on an t
inspection of the fan cooler units and areas outside the concrete shield wall for possible identification of service water leakage.
The inspectica did not identify any leakage in the inspected areas.
__1 6.
Service Water Motor Cocler Returns The licensee was advised of a problem that Unit 2 had found during a review of drawings of the service water system, subsaquent to the flooding incident. The service water cooling return lines from the motor coolers of the fan cooler units in containment did not have a direct means of radiation monitoring as required by the FSAR. The licensee determined that Unit 3 had the identical condition.
-The licensee took immediate action to correct the problem which included the installation of a Radiation Monitor (General Atomic 2 TO) which was attached to a common return line in the pipe penetration area of primary auxiliary building.
The alarm for increases in levels of
.
activity in the return line was placed in the area of the hydrogen reconbiner control panels.
This area is monitored by the nuclear plant operator and logged in control room logs.
i The _ inspector observed the placement of the detector and a test of che alarm function.
The original placement of detector subjected detector
.
.
[-
._;.a_
__
.
_
_ - _. _ _
_.
._ _.
. _ _ _
_
.
.
.
.
.
,
to other fields that would affect readouts. The detector was rcpositioned
.and lead blanketed to read only service water activity.
Calculations were performed on s'te in service water piping by licensee of activity levels vs. detector readouts. Additional review by corporate engineering to verify calcula tions was performed.
This item was reported to the regional office of I&E on January 9, 1981.
A permanent =cnitoring capability is under review by the corporate engineering staf f, as identified in the licensee's confirmatory letter of-January 9, 1981. A review of the permanent modification will be conducted at a subsequent inspection.
,
7.
Review of TMI Lessons Learned Items A review of the Three Mile Island accident by the TMI-2 Lessons Learned Task Force (NUREG 0578) focused on a number of actions that the licensee was required to perform in the area of design and analysis, and plant operations to achieve, in a short term, substantial additional protection required for public health and safety.
The Indian point units had additional ele ents defined in their con-firmatory orders of licensee's commitments of February 11, 1980 which in some cases required additional reduction in time frames to acccm-plish scme of the related items.
.The Resident Inspectors reviewed the status of commitments and made observ-ations of selected installations prior to the licensee's commitment deadlines. The findings were current as of Cecember 15, 1980.
Results of this review are as follows:
--
NUREG 0578 No.
TAP NUMBER TITLE FINDINGS STATUS 2.1.2.b I.A.1.1 Shift Technical Present staff employed Simulator Advisor on Outy on a 24-hour duty basis.
Training Eight Shift Technical Required Advisors in training have 50-286/
completed the academic por-81-01-01 tion of training and are to ccmplete simulator training by 1/1/81. A review of on-site training has been ccm pleted.
Practical on-watch and system familiarization is needed.
2.2.1.a I.A.1.2.
Shift Supervisor The licensee's pres,ent ad-Closed
..
.
f
_
_ _ _.
_
_.
._
_ _ _.._...
._
.
_.
,
.
-
.
.
..
NUREG 0578 No. TAP NUMEER TITLE FINDINGS STATUS Responsibility mistrative procedure does delineate lines of respon-sibility. Minor admints-trative functions are not completely removed f. rom his every-day functions.
This item is considered complete.
(AP-21 Rev. 7)
10/27/31 (AP 21 Rev. 7)
10/2S/30 I.A.1.3 Shift Manning The present administrative Open, One Overtime Limits procedures reflect the Exceptien guidelines of IE Circular 50-286-/
80-02 with one exception; 81-01-02 the licensee f ails to in-clude a minimum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> between work periods.
I.C.1 Short Te-m Completed per confirma:ory Closed Accident and orders as documented per Procedure Re-IE Report 50-235/S0-03.
view 2.2.1.c I.C.2 Shift and Relief Operations department has Coen Turnover Pro-developed shift turnover 50-286/
,_
cedure checklists and A? 21.3 de-S1-01-03 scribes subject matter that is to be discussed during turnover.
IiC : and Maintenance department have no formal methods that require the dis-semination of information to relief shifts.
2.2.1.a I.C.3 Shift Supervisor Licensee has revised pro-Closed Responsibilities cedures to reflect Shif t Suoervisors responsibilities
,
and training has been pro-vided.
(AP 21)
2.2.2.a I.C.4 Control Room Licensee has addressed Closed Access Shift Supervisors re-sponsibilies in itetting C.R. access.
(AP c1)
2.1.3.1 II.D.3 Valve Position Acoustic devices have been Review of Indication, installed and tested on the Environmental P00R ORIGINAL
~
.
.
-.. --
-. - -
-.-
.. -,..~
.-..
.
.
..
.
.
.
NUREG 0578 No. TAP NUMEER TITLE FINDINGS STATUS Relief and three PORV Valves and the Data Safety Valves two safety valves.
In-
'Necessary dication observed by 50-286/
inspectors in the 81-01-04 l
Control Room appears satisfactory.
Temperature in-dication of the down-stream relief and safety valve discharge piping had been previously installed.
Qualification data has not been examined by Inspector for the PCRV requirements.
2.1.7.a II.E.1.2 Auxiliary Auxiliary Feed Systems have Safety
,
'
2.1.7.6 Feed System been partially reviewed per Grade Initiation &
Confirmatory Orders (ISO System Flow day requirements).
Licensee Needed presently considers his 50-286/
system to meat control 81-01-05 grade requirements.
2.1.1 II.E.3.1 Emergency The licensee has addressed Closed Power for the area of pressuri:er heater Pressurizer control function, as a load Heaters on the 480V Vital supply busses.
Backup heaters are stripped upon
--
diesel start, but breakers can be reenergized if sufficient loading i
capacity of the diesel is confirmed.
Procedures PEP RC-6 and PEP EL-1 describe load parameters of the diesels including individual heater loads.
Proredures were examined for suf-t ficient guidelines as to loading capacities of diesel. Tests of
,
loading were conducted and found i
satisfactory. Operator interviews confirmed knowledge of loading sequences.
2.1.5.c Recombiner Two recombiners are Open Procedure installed on the 95'
50-286/
Review and level of contain-81-01-06 Upgrade ment. Test results of the monthly and annual surv-eillance testing have been reviewed by inspectors and found satisfactory.
In-spector verified discharge
.
.
_
-..
- ~ -.
. ~.. -
.
.
.
,
.
NUREG 0578 No. TAP NUMBER TITLE FINDINGS STATUS piping and damper positions.
Further procedure review by the inspector is required.
2.1.4 II.E.4.2 Isolation Licensee has questioned Open Oepend-NRR on clarification of 50-286/
ability requirements of Tap No.
81-01-07 II. E.4.2 and NUREG 0578, 2.1.4 as related to Section 6.2.4 of the Standard Review Plan. NRR response was that clarificiation of position (March 80)
would not be available un-til June 81 with action due by licensee on July 81.
2.1.3.b II.F.2 Instrument-The licensee has installed a Closed ation te Oe-subcooling meter that indicates tect Core psi from saturation. The computer Cooling program has been modified to-eflect this parameter on a CRT readout under all called fur display programs.
Pro-cedure ES-1A, Rev. 9, 1980 re-quires operator attention to sub-coo'.ing saturation points.
_
2.1.1 II.G.1 Emergency PORV's are nitrogen actuated.
Closed Power Sup-Upon isolation of the normal nit-plies for regen supply, emergency nitrogen Pressurizer storage flasks will yield a Relief number of op(ning cycles.
The Valves and closure of valves occurs by the Levels venting of the valve diaphragm by solenoid valves which are powered off the vital instrument buses.
Pressurizer level in-strumentation is powered off instrument buses that are powered from emergency diesels.
.
h mg -
._..__. _.
_. 7. _.
.
.. _... _ _. _, _ _ _
_..
_.
._
_.. -
_
.
..
.
.
..
_
.
0578 No. TAP NUMBER TITLE FINDINGS STATUS 2.2.2.c III A.1.2 Onsite The temporary onsite Open Opera-center has been estab-50-286/
tional lished in the conference 81-01-08 Support room of the PASNY administration Center building. The following de-ficiencies have been noted:
No emergency power to building,
'
Computer parameters frem con-trol room could not be obtained on two occasions when inspected.
Additional training of personnel in the area of computer operation appears necessary and the area may have to be evacuated in case of off gas problems.
'
Additional detailed reviews will be accomplished at a subsequent in-spection of both Category A and B items of TMI 2 Lessons Learned, I
Short Term and Long Term items.
>
8.
Hydrocen Recembiner Test
,
i The licensee performs a fur m:f onal test of the hydrogen recombiners at
'
i refueling intervals. On February 15, 1981, the inspector witnessed the preparation for this test (3PTR-12).
!
Items observed:
valve lineup sampled
--
procedures were available
--
,
inspection of hydrogen recombiner operating panels and units in
!
--
containment was observed i
.i fire protection precautions were examined in containment
--
,
Initial precautions and limitations were reviewed
--
Test Performance ccmments:
t The licensee did not have all initial conditions met to start the
--
test; Fire watch did not know the source of addition'al suppressant
--
water;
Hydrogen recombiner annunciator panel alarms precluded continuation
-
of testing due to lockout feature indication.
(
,
.
.
,. -
_
_,
Ej._u_v._ g _....
.
._,.J'
,_..
___
-=
-
1.
.
.
i.,.x
sc
.
,
.
.
The licensee stated that the test would be performed upon completion of required initial conditions. The licensee conducted the test on
'
.
'
February 22, and 23 with the following outstanding items to be com-
-
plated:
Recalibration of temperature controller
--
Additional recorder calibration to correct problem of determining
[
-
--
ratios of gases.
'
Test resuits have been reviewed and appear to meet test criteria.
l Based on licensee presentation of completed outstanding items, the inspector has no further questions.
9.
Rec. Moffett Staff Members Visit
.
,
On January 29 and 30, 1981, two members of Representative Toby Moffett's staff on the Subcommittee on Environmental, Energy and Resources of
.
the Housa Gcvernment Operations were on the Indian Point site.
Mr. B.
!
Hager and Ms. D. Seyfre: interviewed the Senior Resident Reactor
'
Inspector in the areas of inspection program, inspection criteria and other areas of USSRC Inspection and Enforcement activities.
i 10.
Ion Track Instruments t
The licensee was informed on January 22, 1981 by the resident inspector
,
of.possible leakage found on Ion Track Instrument detectors used on
,
'
explosive cetection devices.
--,
The licensee has in use three No. 75 and three No. 55 detectors. All sources in instruments were swiped (cotton swabs) and found to read
,
less than.001 mei/cm 2 This item will be put on licensee's schedule of i
surveillance. This item is closed.
11. Unresolved Items i
An iter about which more information is required to determine accept-ability is considered unresolved.
Paragraph 7 contains 8 unresolved i
items.
l
12. Exit Interview
At periodic intervals during the course of the inspection, meetings l
were held with senior facility management to discuss the inspection scope and findings.
l
!
I
-
t
,
!
t
.
.
f
.,
.
. _ _
.
,
.1
-
..