ML19209B474
| ML19209B474 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/22/1979 |
| From: | Johnson W, Spangler R, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19209B467 | List: |
| References | |
| 50-313-79-15, 50-368-79-13, NUDOCS 7910090768 | |
| Download: ML19209B474 (15) | |
See also: IR 05000313/1979015
Text
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U. S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEfiENT
REGION IV
Report Nos. 50-313/79-15
50-363/79-13
Docket Nc.
50-313
License No. DPR-51
50-358
License No. NPF-6
Licensee:
Arkansas Fr er ar.d Light Company
,
P. O. Box 551
Little Roc' , Arkansas 72203
<
Facility .are:
Arkansas Nuclear One (AN0), Units 1 and 2
Inspection At:
ANO Site, Russellville, Arkansas
Inspection Conducted: July 8 - August 9,1979
Inspectors:
7 _. I. M I' = - w
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W. D. Johnson, Resident Reactor Inspector
Date
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R: G. Spangler, Refctor Inspector
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G. f . p)'erduzco, Reactor' Inspector
Date
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Sv. R. Dean,RepctorInspector
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R. Smith, Reactor Inspector
Date
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E. A. Cupp, Reactor Insp'ector
Date
Approved By:
7'[<
9/a 2/79
T. F. Westerman, Chief, Reactor Projects Section
Date
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?[0R Dill 81NAL
Inspection Summary
Ins ~ ection conducted during period of July 8 - August 9,1979 (Report No. 50-313/
p
79-15)
Areas Insoscted:
Routine, announced inspection of training, requalification
training. surveillance of pipe support and restraint systems, refueling mainten-
ance, :15c: coerations, followup on previously identified item.s, isothermal
tencera ure coefficient of reactivity measurement, and on-site review committee
activiti es .
The inspection involved 243 inspector-hours on-site by six (6) NRC
inspect:rs.
Results:
aithin the eight areas inspected, one item of noncompliance was
identriec (Infraction - requalification training, paragraph 3).
Inspection conducted during period of July 8 - August 9,1979 (Report No. 50-36C{
79-13)
Areas Insoected:
Routine, announced inspection of plant conditions, training, requal-
ification trafiiing, startup testing, 20% testing plateau data review. The inspection
involved 103 inspector-hours on-site by six (6) NRC inspectors.
Results: Within the four areas inspected, no items cf noncompliance were identified.
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DETAILS
1.
Persons Contacted
J. P. O'Hanlon, ANO General Manager
G.
H. Miller, Engineering & Technical Support Manager
L.
Jexander, QC Engineer
B. '
Eaker, Operations Superintendent
7. i. Cogburn, fluclear Engineer
E. C. Ewing, Production Startup Supervisor
!- w . coma, Scheduler
S. 2 Tenvilliger, Operations and Maintenance Manager
S. Pe rel, Licensing Engineer
F. Foster, Plant Administrative Manager
M. Stroud, Electrical Maintenance Supervisor
R. Eider, I&C Supervisor
J. McWilliams, Planning & Scheduling Supervisor
J. Vandergrift, Training Supervisor
T. Green, Training Coordinator
D. Trimble, Licensing Manager
C. Shively, Plant Performance Engineer
D. Barton, Training Coordinator
The inspectors also contacted other plant personnel, including operators,
technicians and administrative personnel.
2.
Inspector Followup on Previously Identified Items
(Closed) Unresolved Item 313/7703-14 (Inspection Reports 77-03 and 77-18,
paragraph 2):
Perfomance of local leak rate testing of six valves in the
reverse direction.
The inspector reviewed the completed job orders shown below and determined
that the six valves in question had been leak tested in the accident
direction prior to plant startup following the last refueling outage (R3):
Valve No.
Penetration No.
Job Order
SF 44; SF 43
19
7512
.,
CV-1053
70
7540
CV-4446
68
7538
CV-1214; CV-1216
14
7511
(Closed) Unreselved Item 313/7907.-02, 368/7907-02 (Inspection Report 79-07,
paragraph 7A):
Consideration of explosive atmospheres in Procedure 1005.18,
Control of Combustibles.
Revision 1 to Procedure 1005.18, in paragraph 5, requires that the recomen-
dations of NFPA 327-1975 be followed for welding, cutting, grindings, -ets . ,
in an explosive atmosphere.
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4_
$
(Closed)UnresolvedItems 313/7907-05, 368/7907-05 (Inspection Report 79-07,
paragraph 7D):
Define the applicable portions of the QA topical applicable
to the Fire Protection Program.
The "nspector and the senior QC Engineer on site concluded that all portions
of the QA topical, with the exception of vendor qualification criteria and
the annual generic review of the fire protection program, apply to Technical
Sce:ification fire protection hardware and related v;ork. The Safety Review
Ccmittee (SRC) will do the annual generic review of the program rather than
ACSL CA organization.
(Cl sec) Unresolved Items 313/7902-04, 368/7902-13 (Inspection Report 79-02,
paragrapn 4):
Failure of Procedure 1 '4.14 to provide for documentation of
work cescription and post-maintenance
2ckout.
Revision 2 to Procedure 1004.14 implements a revised Job Order form and
includes instructions for its use that specifically addresses the require-
ments of ANSI 18.7.
(Closed) Unresolved Items 313/7822-02; 313/7822-03 (Inspection Report 78-22,
paragraph 4): Operator Errors in the evolution for the recirculation of
tank T-10.
The inspector reviewed the disposition of the licensee's nonconformance report
number 78.
(Closed) Unresolved Item 313/7'"2-22 (Inspection Report 78-12, paragraph 13):
Quorum approval by SRC.
Based on a management meeting between IE Region IV mar gement and AP&L manage-
ment conducted on February 9, 1979, this matter is considered resolved.
(Closed) Open Items 313/7902-02; 368/7902-09 (Inspection Report 79-02,
paragraph 4): The role of the Planning and Scheduling Division in the
issuance and processing of job orders was not called out by procedure.
Procedure 1004.14, Revision 2, Issuance and Processing of Job Orders, now
defines the role of Planning and Scheduling Division with regard to processing
job orders.
(Closed) Open Item 313/7902-01 (Inspection Report 79-02, paragraph 5): Test
and calibration of the Unit 1 Inverter Static Switches.
The inspector reviewed the completed job orders 5849, 5850, 5851, 5852, 5853
and 5054.
These job orders implemented for each inverter static switch TC-1
to procedure 1304.85 which reset the instantaneous overcurrent transfer point
to maximum and the undervoltage transfer point to a minimum.
Each inverter
static switch was tested to ensure that the switch would not transfer for
load increases to 150% and that the undervoltage transfer set point was
approximately 80 volts.
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(Closed) Open Item 313/7909-16 (Inspection Report 79-09, paragraph 9E):
Load analysis of DG-1 with P78 loading.
This analysis was submitted to NRR by AP&L letter dated December 3,1973.
(Clesed) Open Item 313/7909-01 (Inspection Report 79-09, paragraph 6):
Review of acceptance test and environmental qualifications of engineered
safaty features switchgear room chiller units.
The Ms:ector reviewed the startup testing conducted under work plan 71
wnicn was completed Fay 4-5, 1979.
No problems were identified.
Lic2rsing and NRR are corresponding to resolve the questions of environ-
mer. ai ;_alificati ns for the chillers.
IE plans no further followup in
this area unless recuested by NRR.
(Cicsec) Open Item 313/7822-05 (Inspection Report 78-22, paragraph 4):
Operations logs da not show Technical Specification safety limits for
apprcpriate parameters.
The operations log sheets have been reissued to show Technical Specification
limits on the appropriate parameters.
(Closed) Open Item 313/7909-02 (Inspection Report 79-09, paragraph 7):
Improper isolation valve numbers on attachment D to 1104.29, page 5/5.
Permanent change 6 to revision 4 of 1104.29 corrects the isolation valve
numbers for RE 3810.
(Closed) Open Item 313/7909-08 (Inspection Report 79-09, paragraph 7):
Improper realignment steps in procedure 1104.36, supplement 1.
Revision 3 of 1104.36, Diesel Generator Operability, contains the proper
realignment steps to ensure that the Diesel Generators are returned to ESF
standby following surveillance testing.
(Closed) Open Item 313/7909-14 (Inspection Report 79-09, paragraph 7):
Addition of a caution statement in procedure 1004.19 to avoid hanging tags in
a manner which could obscure control board indication.
Permanent change 1 to 1004.19, Caution and Hold Card Tagging, wad the
appropriate caution statement to the procedure.
(Closed) Item of Noncompliance (Inspection Report 313/79-02, paragraph 4):
Failure to perform surveillance testing on P34A (low pressure safety
injection pump) prior to removing P34B from service.
The inspector reviewed Operations iiemorandum 34, dated February 15,1979, and
conducted discussions with two Shift Supervisors and determined that they
were aware of the incident. This completes the followup for the licensee
response.
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(Closed) Open Item 313/7910-07 (Inspection Report 79-10, paragraph 8):
Drawing errors - M402 and M204.
The drawing errors noted in the referenced inspection report have been
Cor*ected.
3.
Tri+c and Recualification Training (Units 1 & 2)
The wroose of this inspection was to evaluate the licensed operator and
Dair:er.arce personnel training program and determine if the training program
was " ccnformar:ce with the regulatory requirements and requalification
trair"ng program approved by fiRC.
The inspector's review included the following points:
The inspector reviewed records for ten licensed operators (RO) of
.
which four were senior operators (SRO).
Annual requalification exams and grades - January through June 1978
.
exams and part of the exams for 1979.
These are presently being
graded and evaluated. The RO's are graded. The SR0's are not
graded.
Records of requalification lecture attendance.
.
Records of on-the-job training, including reactivity manipulations.
.
Records of self-study requalification program topics.
.
Annual operator evaluations and evaluation of actions taken on actual
.
and simulated abnormal and emergency conditions.
Reviewed three lecture lesson plans for Unit 1, and two lecture lesson
.
plans for Unit 2.
Interviewed selected operators from the group of records reviewed.
.
Reviewed requalification program for changes since last f1RC review.
.
Reviewed on-the-job training records for selected maintenance personnel.
.
The inspector reviewed the 1978 annual requalification exams for SR0 and R0's
to determine if the subsequent training program lectures had been scheduled
and conducted for areas where the operators had made a score of less than 80%.
This requalification program is required by 10 CFR 55, Appendix A.
Appendix A, Section 1, states in part that, " Schedule - The requalification
program shall be conducted for a continucus period not to exceed two years,
and upon conclusion shall be promptly followed, pursuant to a continuous
schedule, by successive requalification programs." Section 2 of Appendix A
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further states that the requalification program shall include preplanned
lectures on a regular and continuing basis throughout the license period
in those areas where annual operator and senior operator written exam-
ination indicate that emphasis in scope and depth of coverage is needed.
Ap.cendix A, Section 4.C, requires eko that systematic observation and
evihation of performance and competency of licensed operators and senior
c era: rs by supervisors and/or training staff members, including evaluation
of a:: uns taken, or to be taken during actual or simulated abnormal and
em-rgency conditions. Section 4.2.5 of the requalification program for
Uni: 1. and Secticr 13.2.1 of the Unit 2 FSAR further amplifies the require-
men:: cf the CFR above.
Cen rary to these requirements, a schedule was not provided for these
lectures and requalification programs resulting in lectures not being given
to three licensed operators in areas where weaknesses were noted in the
annual requalification exams. The inspector also found one operator of the
group reviewed that did not have a performance evaluation.
In discussion
with the licensee training coordinator, it was detennined that the perfor-
mance evaluation was not completed. Also, the. training coordinator found
that two additional operators had not had the performance evaluation.
This is considered an item oi .;oncompliance.
(313/7915-05)
,
4.
Pipe Supports (Unit 1)
The inspector examined selected safety-related piping supports and restraints
as well as relevant procedures and records to ascertain whether surveillance
of restraints and supports is being conducted as required by Technical
Specifications, licensee commitments, and approved programs and procedures.
The following procedures were reviewed:
1304.82, Rev.1, 4/4/79, Functional Tes and Calibration ( f
.
Suppressors
1304.84, Rev. 4,1/18/79, Hydraulic Shock Suppressors Visual
.
Inspection
1304.99, Rev. O, 4/7/79, Pipe Hanger Preventive Maintenance
.
Procedure 1304.84 is not considered adequate in that:
a.
The procedure presently includes acceptance criteria but has no
,
operability statement.
b.
The procedure data sheet should direct specific attention to the
condition of the bleed hole, clevis, fasteners and seals, as well as
reservoir level. The data sheet of 1304.84, Rev. 3, included these
observations, but Rev. 4 eliminated them.
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Procedure does not assign specific responsibility for a review of
c.
the snubber visual inspection findings.
Items a. through c. above are considered an open item and will be re-examined
on a subsequent inspection.
(313/7915-01)
Rexrds of snubber visual inspections conducted April 9,1979 and June 19,
1979 w-r3 reviewed.
No items of noncompliance or deviations were
icentified.
The results of the April 1979 functional testing of the following snubbers
were eviewet
r!S-15
55-68
HS-31
HS-69
HS-70
H-C-2
HS-21
HS-49
Acceptance criteria, including lock-up ard bleed velocities, were met in
all cases.
Inspection frequency and sample size were consistent with
'echnical Specification requirements.
The following snubbers were directly examined by the inspector:
HS-1
HS-2
HS-5
HS-7
HS-49
HS-50
HS-82
HS-82 and HS-7 were found to have reservoir levels below 50%.
Further, HS-82
was leaking at the control block and the clevis area had no evidence of
lubrication. The remaining snubbers were in satisfactory condition. This
is an open item.
(313/7915-02)
During the course of the inspection, numerous spring hangers were examined
by the inspector. All were found to be mechanically sound and loaded to
their correct value.
5.
Maior Maintenance Activities (Ilefueling) (Unit 1)
The inspector reviewed the following maintenance activity conducted during
the refueling outage:
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P00RORIBNL
Small ECCS Redesign
This maintenance activity involved cross-connection of HPSI discharge flow
paths to mitigate a small break LOCA coincident with loss of off-site power,
and the failure of one ESF bus, without operator action.
Tne inspector reviewed the Design Change Request (DCR 79-100), the purchase
creers , ard traterial receiving reports concerning the work activities. The
inspector also re,iewed the completed flow test documentation.
(Work Plan 69)
No ': ems of nonccccliance or deviations were identified.
6.
Revis of Plant Operations (Unit 1)
ine inspector reviewed plant logs and records to verify confomance to plant
procedures and to confirm that Technical Specifications were met.
The
inspector also conducted a plant tour of accessible areas to observe general
housekeeping and to verify selected component configurations.
In addition,
the inspector reviewed the licensee's conduct of fire protection inspections.
T:.a following logs and records for June 1979 were reviewed:
RPS Log
NSS Data Point Log
Waste Control Log
ESAS Log
NSS and Safeguard Auxiliary Log
Auxiliary Log, Outside
NSS Hourly Log (Computer)
Station Battery Daily Check
Station tog - Operations
Daily Hot Lab Water Report
Radiochemistry Log
Shift Turnover Log
Jumper and Bypass Log
Caution Tag Log
Hold Card Log
Trouble Tickets
Standing Orders
The inspector noted that there were five (5) outstanding trouble tickets on
the fire detection system and that during the entire week of July 16, 1979,
one of the #1 DG room alarns was in an alarm condition. The licensee
cortmitted to an immediate effort to correct the problems with this system.
(0 pen Item 313/7915-03)
The inspector selected several entries in the Jumper and Bypass Log and the
Tag Logs and with a licensee representative observed those selections to
verify installation was in agreement with the logs.
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The following general observations were made during the plant tour:
No excessive fluid leaks or piping vibrations were observed.
Selected valves were observed to be in the required positions.
.
Selected equipment caution and hold tags were verified to be
.
carrect.
Centrol room operators were knowledgeable in annunciator status.
Zeiected recorders were recording properly.
.
.
?.adiation controls were observed to be established properly.
Control room manning was in accordance with Technical Specifications.
.
Cleanliness was satisfactory.
.
Fire extinguishers were unebstructed and had been currently inspected.
.
Shift turnover was conducted satisfactorily.
.
No items of noncompliance or deviations were noted.
7.
Review of Plant Operations (Unit 2)
The inspectors reviewed plant logs and records to verify conformance to
plant procedures and to confirm that Technical Specifications were met. The
inspectors also conducted a plant tour of accessible areas to observe general
hcusekeeping and to verify selected component configurations.
In addition,
the inspectors reviewed the licensee's conduct of fire protection inspections.
The following logs and records for June 1979 were revieweh
Station Battery Daily Check Log
Station Log - Operations
Auxiliary Operator's Outside Log
CPC/CEAC Auto Restart and Sensor Failure Log
CEA Position Log
Daily Shift Containment Sump Discharge Log
Shutdown Log (Modes 5 and 6)
Control Room Log
Daily Hot Lab Water Report
Radiochemistry Log
Shift Turnover Log
Jumper and Bypass Log
Caution Tag Log
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1
Hold Card Log
l4lt/
Du
Trouble Tickets
Standing Orders
.
.
j
The inspector selected several entries in the Jumper and Bypass Log and
the Tag Logs and with a licensee representative observed these selections
to verify installation was in agreement with the logs.
The following general observations were made during the plant tour:
' c excessive fluid leaks or piping vibrations were observed.
.
Seismic restraints and pipe hangers appeared to be in satis-
.
factory condition.
Selected valves were observed to be in the required positions.
.
Selected equi;=ent caution and hold tags were verified to be
.
correct.
Control recm operators were knowledgeable in annunciator status.
.
Selected recorders were recording properly.
.
Radiation controls were observed to be established properly.
.
Control room nanning was in accordance with Technical Specifications.
.
Fire extinguishers were unobstructed and had been recently inspected.
.
Shift turnover vias satisfactory.
.
In general, plant cleanliness was satisfactory.
However, the inspector noted
two (2) opened quart cans of oil and a closed 55 gallon barrel of Mobil 445
in the north diesel generator room and one (1) opened quart of oil in the
south upper penetration room.
Upon notification, the licensee corrected these
problems.
Unit 2 has a permanent fire watch (security guard) stationed in the 372-foot
level hallway which also includes the entrance to the cable spreading room.
This station will be maintained until the fire protection system is in full
operation.
No items of noncompliance or deviations were noted.
8.
Followup on Licensee Event Reports (Unit 1)
The inspector reviewed the design change packages and work plans associated
with the design changes engineered to correct deficiencies identified in
the following licensee event reports (LER's):
77-19
Inadequate Chiller Units for Engineered Safety Features
Switchgear Rooms
78-09
Possible Inadequacy of HPI Flow for Certain Size Small
Breaks in the RCS
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9.
Review of Isott;ernal Temperature Coefficient of Reactivity Measurement
(Unit 1)
The purpose of this inspection effort was to review the procedures and
results for the measuring of the Isothermal Temperature Coefficient of
Reactivity.
Tre %:cector reviewed Procedure 1302.16, Isotherma? Tempertture Coefficient
Of hea :ivity Measurement.
Data reviewed was that of the latest test con-
cu :ed by the licensee for the above procedure. The inspector noted that
cur'n; the perfcrmance of the Isothermal Temperature Coefficient of Re-
at:te":y test, the controlling rod group was moved in order to increase
raa::cr power within the intermediate range. Although not specifically
pr:nicitea by the above procedure, control rod movement during Temperature
Ccefficient of Reactivity Measurements necessitates that reactivity
associated with rod movement be mathematically accounted for in data
at:alysis. Thus, the rrsults achieved may not be as accurate as is possible
had rod covement and r2 actor power been adjusted prior to the controlled
data runs. A licensee representative indicated that a review of the
procedure would be done to consider these concerns.
fic items of noncompliance or deviation were found.
10.
Followuo to IEB 79-02 (Unit 1)
On May 25, 1979 an inspector observed the torque tests performed by the
licensee for the following supports:
Sucoort
Sketch
HBD-21-H102
12-2178
HSD-14-SW20
12-1457
HBD-14-SWl8
12-1455
HBD-21-H52
12-2161
HBD-21-H60
12-2164
This work was performed according to procedure 11406-276-5.
flo items of
noncompliance or deviations were noted,
11.
Review of 20% Power Plateau Data (Unit 2)
The inspector reviewed the completed test data for 2.800.01, Appendix U,
Unit Load Transient Test, to verify that the licensee had properly evaluated
and approved the test results.
The inspector also reviewed the licensee's evaluation of the 20% power
plateau test results and his authorization to proceed to the next test
plateau. The Plant Safety Conuittee (PSC) and the Test Working Group (TWG)
met jointly on June 12, 1979. At this meeting, the 20% poser plateau test
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i
results were reviewed and found to be acceptable. The PSC Chairman, the
TWG Chaiman and the General Manager signed Step 7.6.6 of Procedure
2.800.01, Power Ascension Test, giving authorization to proceed to the
50.',' power test plateau.
No items of noncorpliance or deviations were identified.
12.
Insrector Witness of Power Ascension Testing (Unit 2)
Th2 in cacter witnessed the performance of an NSSS Calorimetric at the 50%
pcser alateau. The test was performed in accordance with Procedure 2.800.01,
A::crdix I.
This tect determines core thermal powar by means of a secondary
hec: :c!ance ar.d verifies the COLSS thermal power calculations.
Tbc
.spector witr.essed portions of the performance of the isothermal
tem erature coefficient and power coefficient test at the 50% power plateau.
The as was perfcrned in accordance with Procedure 2.800.01, Appendix R.
The irspector witnessed portions of the perfornance of the unit load transient
test at the 50% power plateau. The test was performed in accordance with
Procedure 2.800.01, Appendix U.
The inspector also witnessed portions of the performance of the shape
annealing matrix and boundary condition measurement at the 50% power plateau.
This test was performed in accordance with Procedure 2.800.01, Appendix W.
The inspector noted that during this test, power varied by more than the
+ 0.2% specified by Step W.2.8 of the Procedure. A licensee representative
agreed to evaluate this matter to determine if it could affect test results.
(0 pen Item 368/7913-01)
During the above tests, the inspector verified the following items:
Latest procedure revision in use
.
Minimum crew requirements net
.
Test prerequisites and initial conditions met
.
Procedure is adequate
.
Crew action correct and timely
.
Adequate test coordination
.
Trial data assembled
.
Acceptance criteria met
.
Licensee's preliminary evaluation is adequate
.
The tests were observed to have been adequately conducted.
No items of non-
compliance or deviations were identified.
13.
Onsite Review Comnittee (Units 1 and 2)
The inspector reviewt
the activities of the Plant Safety Committee (PSC) in
order to ascertain whether the Conmittee's review functions are being con-
ducted in accordance with Sections 6.5.1 of the Unit 1 and Unit 2 Technical
Specifications. These sections state the membership, meeting frequency,
quorum, review and record keeping requirements for the PSC.
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The inspector's findings are described below.
a.
The plant Procedure which governs the PSC activities is 1005.01, the
Administrative Controls fianual.
The current revision of this Procedure
(Revision 3, dated January 31,1977) is outdated with respect ta the
description of the PSC Chairman and the titles of the other mmbers.
At the time of this inspection, a revision to this Procedure was in
- reparation. This Procedure was identified as being outdated in a
previcus ir.spection report.
Open items 313/78-22-01 and S63/78-29-01
remain open pending revision of this procedure.
5.
?e preser.t membership and qualifications of the PSC are as required
M the Technical Specifications.
The meeting frequency of the PSC exceeds the Technical Specification
c.
required frequency.
d.
The inspector verified, for selected reviewed items, that those who
participated in the reviews included persons who constituted a quorum
and who possessed expertise in the areas reviewed.
e.
The inspector verified for a selected sample that the items listed in
lechnical Specification 6.5.1.6a through 6.5.1.6j were reviewed by the
PSC as required. The inspector noted that the PSC does not have an
administrative system to assure that the Security Plan and the
Emergency Plan are periodically reviewed as required by the Technical
Specifications.
The Operations and flaintenance !!anager infonned the
inspector that a procedure defining the activities 6nd responsibilities
of the PSC was being developed.
(0penItems 313/7915-04; 368/7913-02)
14.
Containment Purging During flormal Plant Operation (Units 1 & 2)
a.
Unit 1
The licensee received the f1RC letter af fiovember 29, 1978, concerning
containment purging. The licensee's first response to this ietter was
dated January 30, 1979. Thir letter stated an intention to propose a
Technical Specification which will limit purging during operation to
90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per year and ccamitted to limit purging during operation to
90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per year pending review and approval of the proposed Technical
Specification.
This letter further stated that the licensee's review
of safety actuation signal circuitry has not revealed any manual override
features which unintentionally disables additional safety actuation
signal circuits.
The licensee's second response to the above f!RC letter
was dated April 2,1979. This letter proposed a Technical Specification
which would limit containment purging to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per year during plant
operation.
The types of problems described in the tiRC letter of flovember 29, 1978,
relating to potential failures of automatic isolation of the containment
purge isolation valves during power operation do not apply to Af;0, Unit 1.
The Engineered Safeguards Actuation System does not include inputs from
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containment radiation monitors.
The containment purge isolation
valves are closed by Engineered Safeguards channels 5 and 6, which
are actuated by high reactor building pressure. Thus, the problem
of overriding a safety actuation closure signal does not arise at
ANO, Unit 1.
b.
Unit 2
The Technical Specifications of this Unit do not permit opening the
contairnent purge supply or exhaust isolation valves in modes 1, 2,
3 or 4.
Inus, the issue of containment purging during normal plant
cDera:icn dass not apply to this Unit.
15.
IE5/IAL Followuo (Unit 1)
I:2 77-04, Calculational Error Affecting the Design Performance of a System
fcr Controlling pH of Containment Sump Water Following a LOCA:
The Safety Evaluation issued by the Office of fluclear Reactcr Regulation
supporting Amendment tio. 39 to Facility Operating License No. DPR-51
concludes that the licensee's nethodology of pH control is acceptable.
This completes the IE followup for this Bulletin.
16.
Exit Interviews
Exit interviews were conducted at the end of various segments of this
inspecticn with Mr. J. P. O'Hanlon (Plant General Manager) and other
members of the AP&L staff.
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