ML20041A281
| ML20041A281 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/12/1982 |
| From: | Blough A, Cowgill C, Mccabe E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20041A269 | List: |
| References | |
| 50-277-81-27, 50-278-81-30, NUDOCS 8202190374 | |
| Download: ML20041A281 (17) | |
See also: IR 05000277/1981027
Text
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50-277/811105
50-277/811205
50-278/811027
U.S. NUCLEAR REGULATORY COMMISSION
50-278/811109
0FFICE OF INSPECTION AND ENFORCEMENT
50-278/811124
Region I
50-277/81-27
Report No. 50.-278/81-an
50-277
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Docket No. 50-278
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DPR 44
c
f
License No.DPR-56
Priority
Category
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Licensee: Philadelphia Electric Company
2301 Market Street
Philadelphia, Pennsylvania
Facility Name:
Peach Bottom Atomic Power Station, Units 2 and 3
Inspection at:
Delta, Pennsylvania
Inspection conducted:
November 17, 1981 - December 31, 1981
fnspectors:
ll4
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C. J. Cowgiii, III,' Senior Resident Inspector
date signed
W
O"$",
lll'SlU
A. R. Blough, Residerit inspector
date signed
date signed
Approved by:
h
I!II
C. C. McCabe, Jr., Chief, Heactor
date signed
Projects Section No. 28, DRPI
Inspection Summary:ber 31, 1981 (Combined Inspection Report Nos. 50.-277/81-27 and
novemoer u - vecem
50-278/81-30)
Routine, on-site regular and backshif t resident inspection (99 hours0.00115 days <br />0.0275 hours <br />1.636905e-4 weeks <br />3.76695e-5 months <br /> Unit 2;
96.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Unit 3) of:
accessible portions of Unit 2 and Unit 3; operational safety;
event followup; radiation protection; physical security; control room observations;
LER review; IE Bulletins; surveillance; fire protection program status; outstanding
items; and-periodic reports.
Results: Noncompliances: One (Main Steam Line Leak Detection temocrature monitor
setpoints were raised above allowable, Detail 5).
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@202190374 820202
PDR ADOCK 05000277
G
Region I Form 12
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(Rev. April 77)
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DETAILS
1.
Persons Contacted
. W. H. Alden, Engineer-in-Charge, Nuclear Section
W. C. Birely, Senior Engineer, Nuclear Section
M. J. Cooney, Superintendent, Generation Division (Nuclear)
J. K. Davenport, Maintenance Engineer
G. F. Dawson, I&C Engineer
- R. S. Fleischmann, Assistant Station Superintendent
A. Fulvio, Assistant Maintenance Engineer
J. W. Gallagher, Manager, Electric Production
N. Gazda, Health Physics, Radiation Protection Manager
A. Hilsmeier, Engineer, Health Physics and Chemistry
K. W. Hunt, Reactor Engineer
S. R. Roberts, Operations Engineer
D. C. Smith, Outage Coordinator
S. A. Spitko, Site Q. A. Engineer
S. Q. Tharpe, Security Supervisor
- W. T. Ullrich, Station Superintendent
H. L. Watson, Chemistry Supervisor
J. E. Winzenried, Technical Engineer
Other licensee employees were also contacted.
- Present at exit interviews and for preliminary summation of findings.
2.
Previous Inspection Item Update
(Closed) Infraction (278/79-22-02), failure to follow Standby Liquid Control
System valve lineup procedures.
Inspector checks during this and previous
inspections have verified adequate control of these valves. Administrative
procedures have been revised as stated in the licensee's response.
(Closed) Inspector Follow Item (80-03-04 and 80-03-03), verify understanding
of startup check-off list changes pertaining to off-gas radiation monitors.
The
inspector was concerned about the wording of certain procedural steps. The
startup check-off list has since been made more specific regarding off-gas
monitors--a valve line-up is performed before startup, and final adjustments
are made at rated pressure.
This item regarding procedure clarity is closed.
However, additional findings regarding off-gas monitors are detailed in combined
reports 50-277/81-24 and 50-278/81-26.
(Closed) Infraction (80-08-01 and 80-07-01), failure to follow procedures
governing smoking in-plant (reference NRC letter of October 20, 1980 and
licensee responses dated November 19 and December 4, 1980). This matter
was discussed at Employee Refresher Training in the spring of 1980, emphasized
at General Employee Training, and included in a document called " Nuclear Plant
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Rules." This document is issued to each individual upon his first entrance
onsite and at annual refresher training thereafter. The inspector has also
noted increase; use of "No Smoking" signs and clearer designation of smoking
areas.
These ineasures appear to have been effective.
(Closed) Inspector Follow Item (81-07-01 and 81-09-01), railroad door trough
release potential. The inspector reviewed the licensee's " Liquid Leakage
Control Study," dated October 1,1981, and a licensee letter of December 1,
1981. The study addresses potential leakage paths generically, and the letter
details modifications and schedules. Reactor Building railroad doors will be
provided with a dike, and the channels alongside the railroad tracks will be
filled in with grout. These modifications are grouped with numerous others
scheduled for completion by January 1,1983. The licensee indicated that the
railroad door areas modifications would receive top priority within their
group.
These modifications will be subject to post-implementation inspector
review (see next item).
(0 pen) Inspector Follow Item (81-07-05 and 81-09-04), licensee review of
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potential liquid release paths (IAL 81-18 item).
The inspector reviewed
licensee submittals dated October 1 and December 1, 1981. The completed
study appears to meet the objectives of the immediate action letter, and
a schedule for completion of modifications (about 40 total) has been pro-
vided. Most of modifications involve either a change in a drain system or
addition of barriers at doorways.
The inspector will follow licensee prog-
ress on these modifications.
(0 pen) Unresolved Item (81-16-01 and 81-17-01), review of fire protection and
housekeeping in vital pump structure. The licensee has reviewed this item
and initiated "No Smoking" controls and improved housekeeping in the pump
structure. The licensee also stated that administrative procedures regarding
the pump structure and diesel generator buildings would be clarified. This
item remains open.
3.
Plant Operations Review
a.
Logs and Records
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(1) Documents Reviewed
A sampling review of logs and records was spot-checked for accuracy,
completeness, abnormal conditions, significant operating changes and
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trends, required entries, operating and night order propriety, cor-
rect equipment and lock-out status, jumper log validity, conformance
to Limiting Conditions for Operations, and proper reporting. The fol-
lowing logs and records were reviewed.
(a) Shift Supervision Log - November 17 - December 31, 1981
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(b) Reactor Engineering Log, Unit 2 - November 17 - December 31, 1981
(c) Reactor Engineering Log, Unit 5 - November 17 - December 31, 1981
(d) Reactor Operators Log, Unit 2 - November 17 - December 31, 1981
(e) Reactor Operations Log, Unit 3 - November 17 - December 31,'1981
(f) C0 Log Book - November 17 - December 31, 1981
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(g) STA Log Book - November 17 - December 31, 1981
(h) Night Orders - Current Entries
(i) Radiation Work Permits (RWP's) - Various in both Units 2 and 3,
November - December, 1981
(j) Maintenance Request Forms (MRF's) - Units 2 and 3, (Samplin'g)
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November - December, 1981
(k) Ignition Source Control Checklists (Sampling) - November -
December, 1981
(1) Operation Work & Information Data - November - December, 1981
Control room logs were compared against Administrative Procedure A-7,
"Shif t Operations." Frequent initialing of entries by licensed
operators, shift supervision, and licensee on-site management con-
stituted evidence of licensee review.
No unacceptable conditions were identified.
b.
Facility Tours
Daily tours and observations included the following:
-- Control Room - (daily).
-- Ti.rbine Building - (all levels).
-- Reactor Building - (Accessible areas).
-- Diesel Generator Building.
-- Yard and perimeter exterior to the power block, including Emergency
Cooling Tower and torus dewatering tank.
-- Security Building, including CAS, Aux SAS, and control point monitoring.
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-- Lighting.
-- Vehicular Control.
-- The SAS and power block control points.
-- Security Fencing.
-- Portal Monitoring.
-- Personnel and Badging.
-- Control of Radiation and High Radiation areas, including locked door
checks.
-- TV Monitoring Capabilities.
-- Shift Turnover.
Off-shift inspections and areas examined follow:
DATE
AREAS EXAMINED
November 24
Control Room
November 27
Control Room, Unit 2 Reactor Building
and Refuel Floor, Turbine Building,
Protected Area
December 3
Control Room
December 4
Protected Area, Pump Structure,
Control Room, Unit 2 Reactor Building
December 9
Control Room
December 15
Control Room, Turbine Building
' December 16
Protected Area lighting
-- Off-Normal Alarms. Selected annunciators were discussed with control
room operators and supervision to assure they understood plant condi-
tions and that corrective action, if required, was being taken. The
operators were knowledgeable of alarm status and plant conditions.
Increased staff attention. to malfunctioning annunciators was apparent.
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-- Control Room Manning. Staffing frequently was checked against 10'CER
50.54(k), the Technical Specifications, and commitments 'to the NRR
letter of July 31, 1980.
Presence of a senior licensed operator in
the control room complex was frequently verified.
No unacceptable
conditions were identified.
-- Fluid Leaks.
The inspector observed sump status, alarms, and pump-
out rates, and discussed leakage with licensee personnel.
No viola-
tions were identified.
-- Piping Vibration.
No significant or unusual piping vibration was
identified.
-- Monitoring Instrumentation. The inspector frequently confirmed that
selected instruments were operating and indicated values were within
Technical Specification requirements.
Daily, when the inspector was
on site, ECCS switch positioning and valve lineups, based on control
room indicators and plant observations were verified.
Observations
included flow setpoints, breaker positioning, PCIS status, radiation
monitoring instruments, and process computer printouts-
No unacceptable
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conditions were identified.
-- Equipment Conditions. The inspector verified operability of selected
safety equipment by in-plant checks of valve positioning, control of
locked valves, power supply availability and breaker positioning.
Selected major components were visually inspected for leakage, proper
lubrication, cooling water supply, operating air supply, and general
conditions.
Systems checked included Unit 3 Standby Liquid Control,
Unit 2 Core Spray 'A'
and
'C', and Unit 3 Core Spray 'B'
and 'D'.
Selected Emergency Service Water System valves were also checked.
The
inspector reviewed selected blocking permits (tagouts) for conformance
to licensee procedures.
Breaker, switch, and valve positioning was
verified.
Included were:
Permit No.
Equipment
3-7
Recirc pump MG Set Hoist (30H06)
2-23-M1-4
Unit 2 HPCI Gland Seal Blower
-- Fire protection.
The inspector frequently checked fire protection
measures.
He observed control room indications for fire detection
and fire suppression systems, spot-checked for proper use of fire
watches and ignition source controls, checked a sampling of fire
barriers for integrity, and observed fire-fighting equipment stations.
No violations were identified.
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4.
IE Bulletin Response -- IE Bulletin 80-14, " Degradation of Scram Discharge
Volume Operability"
This bulletin related instances of scram discharge instrument volume (SDIV)
level switch failures and drain valve slow closures. . Licensees were to
report history of level switch and vent / drain valve failures, invoke SDIV
vent / drain valve operability and testing requirements, and ensure surveil-
lances are adequate to detect SDIV level switch degradation. The inspector
reviewed the licensee's responses, dated July 25, 1980 and September 29,
1981, and the following licensee procedures:
-- ST 9.1-2, revision 18, May 20,1981, "The Surveillance Log"
-- ST 9.1-3, revision 23, September 21, 1981, "The Surveillance Log"
-- ST 9.22, revision 6, September 11, 1981, " Scram Discharge Volume Drain
and Vent Valve Stroking
(Unit 2 only)"
-- ST 9.22A, revision 0, September 21, 1981, " Scram Discharge Volume Drain
and Vent Valve Stroking"
Vent and drain valve position is logged each shift; procedures require prompt
fiRC notification in event of valve inoperability of over an hour.
Valves are
stroked daily at Unit 2 and monthly at Unit 3, which has . redundant valves.
fiRR accepted the licensee's bulletin response in a generic safety evaluation
of BWR scram discharge systems, December 1, 1980.
Proposed Technical Speci-
fications in this area are under f4RR review.
The inspector had no further
questions regarding this bulletin.
5.
Review of Licensee Event Reports (LER's)
The inspector reviewed LER's submitted to fiRC:RI to verify that the
a.
details were clearly reported, including the accuracy of the description
of cause and adequacy of corrective action.
The inspector determined
whether further information was required, generic implications were in-
dicated, or the event warranted onsite followup.
The following LER's
were reviewed:
LER flos.
LER Date
Event Date
Subject
3-81-16/3L
December 2, 1981
October 27, 1981
RCIC turbine speed
control problems,
corrected by governor
adjustments
2-81-44/3L
December 3, 1981
14ovember 5,1981
E-1 Diesel failed to
start
3-81-17-3L
December 9, 1981
tiovember 9, 1981
RCIC High Steam Flow
isolation switch set-
point drifted high
and was recalibrated
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LER No.
LER Date
Event Date
Subject
- 2-81-46/IP
December 7, 1981
December 5, 1981
Main steam line. tunnel
and IT
December. 18, 1981
high temperature set-
points were raised
above allowable limits
- 3-81-18/3L
December 24, 1981 November 24, 1981 HPCI turbine supply valve
blown fuse
- denotes reports selected for onsite followup.
b.
For LER's selected for onsite review (denoted by asterisks above),
the inspector verified that appropriate corrective action was taken
or responsibility assigned and that continued operation of the facility
was conducted in accordance with Technical Specifications and an un-
reviewed safety question as defined in 10 CFR 50.59 was not involved.
Report accuracy, compliance with current reporting requirements and
applicability to other site systems and components were also reviewed.
(1) LER 2-81-46/IP and IT
On December 5,1981, licensee exceeded the Limiting Condition for
Operation (LCO) for Main Steam Line Leak Detection Temperature
Monitor setpoints for about 20 minutes. The LC0 requires a trip
setpoint of less than or equal to 200 degrees Farenheit.
Background: The temperature monitors are provided to detect and
isolate main steam line leaks.
The licensee has observed that,
when the ventilation is reduced in the main steam tunnel, the ambient
temperature in the area surrounding the detectors increases and will'
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approach the trip setpoint.
Further, when normal ventilation is
restored, hot stagnant air in the tunnel is drawn past the in-duct
sensors, causing a brief temperature transient at those sensors.
Following a loss of Reactor Building ventilation in January 1981, the
licensee obtained a one-time Emergency Technical Specification Change
to allow temporarily raising setpoints to 250 degrees Farenheit while
restoring Reactor Building ventilation.
In June 1981, the licensee requested a permanent Technical Specification
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change to pennit use of the higher setpoints for up to 30 minutes during
ventilation system restart.
Event Description: About 6:00 p.m. on December 5,1981, preparations
were made for regeneration of a Reactor Water Cleanup demineralizer.
These preparations included shifting demineralizer area ventilation
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to the Standby Gas Treatment System, which involves securing certain
normal ventilation fans. About 8:00 p.m., the 'A' Main Steam Line
Tunnel High Temperature channel alarmed and channel 'A' Group I
isolation tripped. The other channels were found to be above normal
and approaching trip setpoints. After determining that a ventilation
problem existed, the Shift Superintendent directed that the setpoints
of the steam line high temperature trips be adjusted to 250 degrees
Farenheit in order to restore Reactor Building ventilation without
causing a Group I isolation and scram.
After about 20 minutes ven-
tilation had been restored, and the setpoints were re-adjusted to
195 degrees Farenheit.
Causes and Circumstances: The inspector discussed the event with
shif t personnel and station management and reviewed shift operating
' logs to determine the. circumstances surrounding the event. All
operators believed, during the event, that the proposed Technical
Specification change had been approved, authorizing actions taken.
The inspector reviewed systems procedure S10.5.G., Revision 0,
November 3, 1976, " Manual Swap-0ver of Reactor Building Equipment
Exhaust to Standby Gas," with control room operators, and noted
that the procedure was not followed when making the ventilation
system lineup, in that actions requiring entry into the Standby
Gas treatment room were not performed. A licensee representative
stated that the procedure is under revision; this area will be re-
inspected (277/81-17-01).
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Control Room operators stated that one channel ' A' detector wah the
alarm condition, and one channel
'B' detector indicated about 190
degrees Farenheit. All setpoints were about 195 degrees Farenheit.
The Shift Superintendent stated that he quickly reviewed the Tech-
nical Specifications and then had the setpoints adjusted.
He thought
his actions were allowed, although he had not seen the statement dur-
ing his review. After the setpoints had been adjusted, the station
Engineer--Operations was consulted, and it was recognized that author-
ity to change setpoints had not been granted by NRC.
Discussions with
operators involved indicated main steam tunnel temperatures increased
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about six degrees Farenheit when ventilation was restored.
Further discussion showed that when the auxiliary operator established
the initial ventilation lineup at 6:00 p.m., actual ventilation system
conditions (which provided inadequate main steam line tunnel flow)
were not understood by the Unit 2 Reactor Operator. The licensee
attributed this misunderstanding to inadequate communications.
Conclusions:
Raising Main Steam Line Leak Detection Temperature
setpoints above 200 degrees Farenheit is contrary to Technical Specification 3.2.A and is a violation (277/81-27-02).
Shift per-
sonnel acted in accordance with a proposed Technical Specification,
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unawarethat NRC review, safety evaluation, and approval of the speci-
fication had not been completed. Such licensee action can thwart the
NRC safety review process. The inspector expressed concern to licen-
see management regarding the failure to know and follow the require-
ments of the Technical Specifications and regarding the repetitive
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violation of Limiting Conditions for Operation.
The inspector noted
that the licensee's Technical Specification Amendment request was
granted on December 16, 1981.
(2) LER 3-81-18/3L - For this event, the inspector reviewed testing of
redundant equipment, observed portions of testing, and checked com-
pleted tests (Detail 6).
No violations were identified.
6.
Surveillance Testing
The inspector observed surveillance to verify that testing had been properly
approved by shift supervision, control room operators were knowledgeable re-
garding testing in progress, approved procedures were being used, redundant
systems or components were available as required, test instrumentation was
calibrated, work was performed by qualified personnel, and test acceptance
criteria were met.
Parts of the following tests were observed:
-- ST 6.8, revision 21, June 2, 1981, "RHR 'A' Pump, Valve, Flow and Unit
Cooler Function," performed November 24, 1981; and
-- ST 2.10.27, revision 0, September 8,1981, " Functional Check of ECCS
B/D-2 Card File" performed December 22, 1981.
The inspector reviewed completed documentation for the following tests
performed November 24, 1981 during HPCI system maintenance:
-- ST 1.8, revision 0, May 22, 1981, " Automatic Blowdown System 'A' Logic
System Functional Test."
-- ST 1.9, revision 9, May 22, 1981, " Automatic Blowdown System 'B' Logic
System Functional Test."
-- ST 6.11, revision 20, August 24,1981, "RCIC Pump, Valve, Flow, Cooler."
The inspector reviewed completed test ST 7.1.1, revision 8, January 3,1980,
" Standby Liquid Control Tank Boron Solution Concentration," performed to
meet the monthly test requirements on December 22, 1981.
The inspector
verified that test data was complete and conformed to Technical Specification
requirements.
The inspector also verified that the procedure was properly
approved.
No violations were identified.
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7.
Radiation Protection
During this report period, the inspector examined work in progress in both
units, including the following:
a.
Health Physics (HP) controls
b.
Badging
c.
Protective clothing use
d.
Adherence to RWP requirements
e.
Surveys
f.
Handling of potentially contaminated equipment and materialc
More than 40 people observed exiting various RWP areas, the power block, and
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the licensee's final exit point met frisking requirements of Health Physics
procedures. A sampling of high radiation doors was verified to be locked as
required.
No violations were identified.
8.
Physical Security
The inspector spot-checked compliance with the accepted Security Plan and
implementing procedures, including: operations of the CAS and SAS, over 20
spot-checks of vehicles onsite to verify proper control, observation of
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protected area access control and badging procedures, inspection of physical
barriers, checks on control of vital area access and escort procedures.
No violations were identified.
9.
The inspector reviewed correspondence and discussed with licensee engineers
the status of various fire protection program requirements and commitments.
The requirements were included in Table 3.1 of the Safety Evaluation Report
(SER) to Technical Specification Amendments 53 (DPR-44) and 53 (DPR-56),
dated May 23, 1979. Table 3.2 of the SER contained items requiring additional
information from the licensee--subsequent correspondence resulted in additional
commitments (listed in supplements to the SER) on these items.
Further require-
ments were promulgated in Appendix R to 10 CFR 50, effective February 17, 1981.
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The following is a summary of the status provided by the licensee; inspector
verification has not yet been done.
a.
SER Requirements and Commitments
SER-Item No.
Description
Status
3.1.1
Fire Detection Systems
. Design details were submitted and
approved.
Licensee correspondence
dated October 14, November 13, and
November 19, 1981, requested exemp-
tion from the November 19 implemen-
tation date until January 19, 1982.
The NRC:NRR Licensing Project Man-
ager (LPM) stated that NRR concurs
with the exemption and is prepar-
ing a response. . Compensatory
measures are in effect.
3.1.2
Water Suppression Systems Complete, with the exception of
recirculation pump motor gener-
ator rooms, whose status is the
same as Item 3.1.1.
3.1.3
Hose Stations
Complete
3.1.4
Portable Extinguishers-
. Complete
3.1.5
Fire Doors
Complete
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3.1.6
Ventilation Equipment
Complete
3.1.7
Fire Barrier Penetra-
NRC-letter of November 24, 1980
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tion 3eals
integrated this item with Sections
III.G and III.M of-10 CFR 50,
Appendix R.
Licensee correspond-
ence dated March 20 and October 14,
1981 now under NRR review, proposes
a completion date of March 1,1984.
3.1.8
Air Breathing
Complete
Equipment
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3.1.9
Complete
3.1.10
Communications
Complete
3.1.11
Control of Combustibles
Complete
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SER Item No.
_ Description
Status-
3.1.12
Fire Hydrants
Complete
3.1.13
Hose Cart Houses
Complete
3.1.14
Administrative Controls
Complete
3.1.15
Fire Water SystemL
Complete .
' Valve Supervision
3.1.16'
Diesel Fuel Tank
Complete
Fill Connection
3.2.1
Safe Shutdown Analysis
Licensee letter of March 20, 1981
commits to submittal detailing
required modifications by March 1,
1982, and completion of modifica-
tions by March 1, 1984 (10 CFR 50,
Appendix R,Section III.G also
applies).
3.2.2
Cable Separation
NRC letter of November 24, 1980
Criteria
integrates this item with Section
III.G of 10 CFR 50, Appendix-R.
Status is the same as Item 3.2.1.
3.2.3
Fire Detection Systems
Complete, excluding certain fire
zones for which additional de-
tectors are needed.
For these
zones the status is the same as
,
for Item 3.1.1.
The licensee
provided a list of additional
detectors (10 CFR 50 Appendix R,
Section III.F also applies).
3.2.4
Water Suppression Systems Same as 3.1.1.
3.2.5
Gas Suppression Systems
Same as 3.1.1.
3.2.6
Fire Doors
Complete, except for electrical
supervision of certain fire
doors, whose status is equiva-
lent to Item 3.1.1.
3.2.7
Interior Hose Stations
Complete
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SER-Item No.
Description
Status
3.2.8
Fire Penetration Seals
Open pipe penetration aspects are
complete. Other aspects have the
same status-ds Item 3.1.7.
3.2.9
Ventilation Ducts
Complete-
3.2.11
Forcible Entry Tool
Complete
3.2.12
Exterior Hose Tests
Complete
3.2.13
Hose House
Complete
3.2.14
Complete
3.2.15
Hydrant Fittings
Complete
b.
10 CFR'50,' Appendix R (February 19,1981) Requirements
Many of the requirements of this regulation had been previously established
in the fire protection SER (May 23, 1979) and supplements.
In a letter
dated March 20, 1981, the licensee stated he was in compliance with all
items of 10 CFR 50, Appendix R, except for Sections III.F. G, H, K, L, M
and N.
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Section
Descriptiqn
Status
III.F
Automatic Fire Detection
Additional detectors were
deemed necessary.
Status is
equivalent to SER Item 3.1.1.
III.G
Safe Shutdown Analysis
Same as SER Item 3.2.1
III.H
Fire Brigade
Complete, excluding air bottle
charging system, whose status
is the same as SER Item 3.'1.1
III.K.
Administrative Controls
Complete
III.L
Alternative and Dedicated Same asSection III.G
Shutdown Capability
III.M
Same asSection III.G
Seal Qualification
III.N
Fire Doors
Same as SER Item 3.2.6
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10.
In-Office Review of Periodic and Special Reports
The following licensee reports have been reviewed in-office onsite,
a.
Peach Bottom Atomic Power Station Monthly Operating Report for:
October 1981, dated November 16, 1981
November 1981, dated December 15, 1981
These reports were reviewed pursuant to Technical Specifications, and
. verified to determine that operating statistics had been accurately
reported and that narrative summaries of the month's operating exper-
ience were contained therein. The inspector noted that, in the Unit 2
operating status section of the October report, information regarding
shutdowns scheduled over the next six months had been omitted. A li-
censee representative indicated that .the information would be telephoned
to NRC Headquarters for inclusion in the " Licensed Operating Reactors
Status Summary Report."
b.
Thermal Mapping Report No. 81-6 dated November 23.
This report was
reviewed pursuant to Environmental Technical Specifications to verify
that the required information had been submitted to NRC:NRR.
The
reports forwarded isotherm surveys for October 26, 1981.
No violations
were identified.
11. Management Meetings
a.
Preliminary Inspection Findings
A summary of preliminary findings was provided to the Station Superin-
tendent at the conclusion of the inspection.
During inspection, licen-
see management was periodically notified of the preliminary findings by
the resident inspectors.
The dates involved, the senior licensee rep-
resentative contacted, and subjects discussed follow:
Date
Subject
Senior Licensee Representative Present
December 4
Routine discussions
Station Superintendent
December 7
Recent NRC Enforce-
General Superintendent, Nuclear
ment History and
Generation Division
LER 2-81-46/IP
December 11
Routine discussions
Outage Coordinator
December 14
Station Superintendent
Appraisal Status
December 15
Station Superintendent
Appraisal Pre-
liminary Findings
i
a
.- .
. _ . _ _ _ _ _ _ _ _ _ _ .
_
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
. .
.o.
.
.
16
Date
Subject
Senior Licensee Representative Present
December 22 ' Routine discussion
Station Superintendent
December 28
Routine discussion
Station Superintendent
January 8,
Summary of Findings.
Station Superintendent
1982
b.
Attendance at Management Meetings Conducted by Region-Based Inspectors
The. resident inspectors attended entrance and exit interviews by region-
based inspectors as follows:
Inspection
Reporting
Date
Subject
Report No.
Inspector
December 7
277/81-28
R. DeFayette
Appraisal
278/81-31
December 17.
277/81-28
R. DeFayette
278/81-31
December 21
Surveillance
277/81-29
N. Blumberg
Testing
278/81-33
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