ML19261E874
| ML19261E874 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/23/1977 |
| From: | Davis A, Durr J, Fasano A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19261E857 | List: |
| References | |
| 50-289-77-05, 50-289-77-5, 50-320-77-09, 50-320-77-9, NUDOCS 7910170919 | |
| Download: ML19261E874 (47) | |
See also: IR 05000289/1977005
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(1 J75) (Rev)
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U. S. NUCLEAR REGULATORY CC10iISSION
OFFICE OF INSPECTION AND E'iFORCDfENT
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REGION I
50-289
IE Insp. ction Report No:
50-289/77-05 and 50-320/77-09
Docket No:
50-320
Licensee:
Metropolitan Edison Company
License No:
P. O. Box 542
Priority:
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C
Readino, Pennsylvania 19603
Category:
B-1
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Safeguards
Location:
Middletown, Pennsvivania (Three Mile Island)
Unit 1:
Type of Licensee:
Unit 2:
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Ty" of Inspec tion:
Routine, Announced
a
February 22-25, 1977
Da ) of Inspection: _
Unit 1
Dates of Previous Inspectio1:
February 17-18,1977- and 2
Reporting Inspector:
b . / /k,s
3/23/77
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ArR. Fasano, Reactor Inspector
DAIE
//p4 %
3/E3/77
Acconpanying Ins ectors:
.
.
M
Durr
eactorInsdiletr
DATE
FOr
3/2.? /n
' DME
W/A.
'n
eago
specto
-w V-
3/23 /7?
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DATE
J/T. Smiff, Reactor [nsp
or
Ci , 4 % -
c.,
Other Acconpanying PersonneI:
o i
s neseard _ paar+,r rne,ac+or
tets/ ,
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DATE
Reviewed By: Q1Mhm
-Y3!II
n, e-
A. B. Davis, Chief, Reactor Projects Section No.1,
DATE
Reactor Operations and Nuclear Support Branch
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SUMMARY OF FINDINGS
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Enforcement Action
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Infr actions
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77-05-01. Failure to take corrective action in accordance with commit-
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ments to the NRC contrary to 10 CFR 50, Appendix B, Criterion XVI and
the accepted Operational Qu .lity Assurance Plan (FSAR Section 1A)
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Section 6.7.
(Details S.a and 8.b)
,
Unit 2
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77-09-01, Failure to establish / document measures and failure to correct
conditions adverse to quality as soon as practicable contrary to 10 CFR 50, Appendix B, Criterion XVI and the accepted Operational Quality Assur-
ance Plan (FSAR Section 17.3) Section 17.3.2.
(Detail 18.a)
(])
Licensee Action on Previously Identified Enforcement Items (Unit 1)
)
Corrective actions taken in response to NRC:I Inspection Reports
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50-289/76-11 and 50-289/76-19 had not been completed in accordance
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with the licensee's commitments.
(Details 8.a and 8.b)
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Corrective action taken in response to NRC:I Inspection Report
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50-289/76-25 has been completed.
This item, 76-25-1, is resolved.
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(Detail 8.c)
Desion Chances
None rep';rted.
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Unusual Occurrences
None reported.
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Other Significant Findings
A.
Current Findings
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1.
Acceptable Areas
(These are items which were reviewed on a sampling basis and
findings did not involve any Items of Noncompliance, Deviations,
.
or Unresolved Items except where noted.)
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Unit 1
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Nonroutine Event Reports.
(Detail 3)
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Seismic Qualification of Steam Generator Level and Pressure
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Indications.
(Detail 4)
IE Bulletin / Circular Followup.
(Detail 5)
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Safety Limits, Limiting Safety ' stem Settings, and
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Limiting Conditions for Operation.
(Detail 6)
C)
Plant Operations.
(Detail 7)
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Corrective Action for Previously Identified Enforcement
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Items.
(Detail 8)
Previously Reported Unresolved /Other Items.
(Detail 9)
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Unit 2
Receipt, Storage, and Handling.
(Detail 11)
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Tests and Experiments.
(Detail 12)
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Design Changes.
(Detail 13)
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Surveillance Testing and Calibration.
(Detail 15)
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Preoperational Test Records.
(Detail 17)
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Startup and Test quality Assurance Program.
(Detail
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18.b)
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2.
Varesolved Items
Unit 1
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77-05-02, DH-V1 Supplemental Engineering Report and Val se
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Repair Schedule.
(Detail 3.c(1))
77-05-03, Replacement of OPLS Switches and Revision of
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Procedure 1301-8.2.
(Detail 3.c(3))
77-05-04, Special Test Procedure for Testing the Reactor
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Building Spray System.
(Detail 5.b)
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77
3-05, Complette
of Revision Documentation of Limitorque
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Ad. 2stment Procec'
(Detail 5.d)
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77-05-06, Controls over Safety Related Censumable Material .
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(Detail 7.b(6))
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77-05-07, Revision of AP 1001 to Establish a Program for
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Review of Safety Related Facility Procedures.
(Detail
8.a.)
See 77-05-01.
77-05-08, Completion of I&C and Electrical Maintenance
G)
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Personnel Training on AP 1013.
(Detail 8.b.)
See 77-05-
01.
77-05-09, Review of NRC:I Inspection 50- 39/76-08 Item of
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Noncompliance by GORB.
(Detail 9.c)
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77-05-10, Record Storage Inadequacies.
(Detail J.e)
77-05-11, Hausekeeping Procedure.
(Detail 9.k)
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77-05-12, Revise Prot eduro AP 1016 to Specify How Modifica-
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tions Are sent to Training.
(Detail 9.p)
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77-05-13, Determine Adequacy of Response to Circular 76-
06.
(Detail 5.b)
Unit 2
77-09-02, Requirement by QA Procedure to addr_ss minimum
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documentation criteria for Certificates of Conformance.
(Detail 10.a)
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77-09-03, Issue Station Administrative Procedure 1020 to
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cover Control of Housekeeping and the Establishment of
Housekeeping Zones.
(Detail 14)
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77-09-04, Consumable Items to be Listed on the New QA
Systems List for TMI-2.
(Detail 16)
3.
Inspector Followup Items
Unit 1
77-05-12, Status of Procedure Change Request Completions.
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(Detail 9.r)
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77-05-13, Log Sheet Notation Reference to TS.
(Detail
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7.a(1))
77-05-14, Protective Clothing Distribution Point Problem.
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(Detail 7.b(2))
Unit 2
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77-09-05, Unit 1 Extraction. Steam for Unit 2, Procedures.
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(Detail 19)
B.
Status of Previously Identified Unresolved Items
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Unit 1
1.
The following items have been resolved:
a.
Item 76-01 (Detail 13.b.(8)) and 76-17 (Detail II.11),
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GORB Review of TS and License Violations Delineated in
NRC:I Inspection Reports for Calendar Year 1975.
(Detail
9.a)
b.
Item 76-10 (Detail 3.b.(1)(b)), Radiation Chemistry Tech-
nician Training on Precedure HP 1631.
(Detail 9.b)
c.
Item 76-15 (Detail 21), Reactor Building Purge System.
(Detail 9.d)
d.
Item 75-14 (Detail 12.b), Record Storage Inadequacies. .
(Detail 9.e)
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e.
Item 76-24-2, FSAR Change for RCP Monitor Delay Time.
(Detail 9.f)
f.
Item 76-24-3, Additional Evaluation of ER 76-18/1T.
(Detail 9.g)
g.
Item 76-24-4, Repair of Valve MU-V28.
(Detail 9.h)
h.
Item 76-24-5, Long Term Corrective Action for ER 76-28/4T
and 76-35/1T.
(Detail 9.i)
1.
Item 76-24-10, GORB Review of Reportable Occurrences.
(Detail 9.j)
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Item 76-24-12, Revision of Procedure GP 4015 to Include
Crite:ia on Due Date Fxtensions.
(Detail 9.1)
k.
Item 76-24-13, Revise Procedure GP 4015 to Include Criteria
on Closecut.
(Detail 9.m)
1.
Item 76-24-14, Verify that Audit Report 75-25 is available
at Site QC Files.
(Detail 9.n)
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Item 76-24-15, Revise GP 4407 to Designate Duplicate QC
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Record Storage Requirements.
(Detail 9.o)
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Item 76-24-17, Verify Completion of Corrective Action on
(Detail 9.q)
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2.
The following items remain unresolved:
Unit 1
a.
Item 76-10 (Detail 8.b.(4)) and 76-17 (Detail II.10.d),
GORB Review of License Violations Delineated in NRC:I
Inspection Report 50-289/76-08.
(Detail 9.c)
This item is redesignated as Item 77-05-09.
b.
Item 76-24-11, Housekeeping Procedure.
(Detail 9.k)
This item is redesignated as Item 77-05-11.
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c.
Item 76-24-16, Revise Procedure AP 1016 to Specify How
Modifications are Sent to Training.
(Detail 9.p)
This item is redesignated as Item 77-05-12.
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Management Interviews
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Unit 1
Entrance Interview
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An entrance interview was conducted at the site, Unit 1, on February 22,
1977, with the Unit 1 Superintendent and the Unit 1 Supervisor of Opera-
tions. The inspector described the scope, estimated duration, personnel
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to be contacted, and records to be reviewed as part of the inspection
on Unit 1.
The licensee was informed that a Unit 2 QA oriented inspection
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would be conducted at the Met Ed Corporate Headquarters.
Unit 2
Entrance Interview
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An entrance interview was conducted at Met Ed Corporate Headquarters on
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February 23, 1977, with the Supervisor of Quality Assurance and the Section
Head of Licensing.
During the meeting the inspector described the scope,
estimated duration, personnel to be contacted, and records to be reviewed
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as part of the inspection on Unit 2.
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Exit Interviews
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Three exit interviews were conducted.
A.
The first exit was held at the Unit 1 plant, February 2E,1977.
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The items discussed are described in the details of this report
designated as affecting Unit 1.
The licensee attendees are desig-
nated with asterisks by their name as listed in Detail 1, Persons
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Contacted.
B.
The second exit was held at the Unit 2 GPU trailer complex onsite,
February 25, 1977.
The items discussed are described in Details
17,18, a nd 19.
The licensee attendees are designated in Detail 1,
Persons Contacted,
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C.
The third exit was held at the Met Ed Corporate Headquarters, Read-
ing, Pennsylvania on February 25, 1977, at the conclusion of the
inspecticn with the following licensee attendees:
Metropclitan Edistn Company (Met Ed)
Mr. L. L. Lawyer, Manager, Operational Quality Assurance
Mr. W. E. Potts, Section Head, Licensing
Mr. R. N. Prabhaker, Supervisor, Quality Assurance
The scope and objectives of the inspection were discussed and the
inspection findings were presented as detailed in this report,
specifically the Items of Noncompliance and those items related
to Unit 2 Quality Assurance Prcoram.
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DETAILS
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Persons Contacted
General Public Utilities Service Corporation (GPUSC)
- Mr. R. F. Fenti, Quality Assurance Auditor
- Mr. P. A. Levine, Quality Assurance Auditor
- Mr. M. A. Nelson, Technical Engineer
- Mr. M. J. Stromberg, Chief Quality Assurance Auditor
- Mr. R. J. Toole, Test Superintendent
Mr. J. E. Wright, Site Quality Assurance Manager
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United Engineers and Constructors, Incorporated (UE&C)
Mr. S. Bailey, Mechanical Engineer
Mr. R. Barley, Lead Mechanical Engineer
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Mr. B. A. Bozarth, Quality Control Phase II Engineer
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Mr. R. T. Carlson, Test Engineer
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Mr. S. Kakarla, Lead Engineer
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- Mr. D. C. Lambert, Field Supervisor, Quality Control
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Mr. D. R. Rayne, tead Mechanical En9 neer
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Metropolitan Edison Company (Met Ed)
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Mr. M. Beers, Shift Supervisor
- Mr. R. Bensel, Electrical Engineer
Mr. S. H. Bonneville, Administrative Assistant, Quality Control
Mr. T. Book, Shift Foreman
Ms. R. Brown, Technic?.1 Analyst, Generation Engineering
Mr. J. Chwastyk, Shift Supervisor
- Mr. J, J. Colitz, Unit I Superintendent
- Mr. W. W. Cotter, Supervisor, Quality Control
Mr. E. Crawford, Electrical Maintenance Foreman
Mr. T. Crouse, Control Room Operator
Mr. B. Deiter, Control Room Operator
Mr. D. Dubiel, Acting Supervisor, Radiation Protection and Chemistry
Mr. J. Fritzen, Senior Engineer
- Present at Unit 1 exit interview
- Present at Unit 2 exit interview
- Present at both Unit 1 and 2 exit interviews
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Mr. J. Hall, Inservice Inspection Engineer
n '. C. E. Hartman, Lead Electrical Engineer
Mr. E. V. Kellogg, Technical Analyst III
- Mr. G. A. Kunder, Unit I Supervisor of Operations
Mr. R. G. Kobstein, QA Engineer II
Mr. L. L. Lawyer, Manager, Quality Assurance
l%. G. A. Loignon, Jr., Engineer I
- Mr. T. Mackey, Engineer II, Nuclear
Mr. J. Masters, Auxiliary Operator
- Mr. G. P. Miller, Unit 2 Superintendent (by phone only)
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Mr. H. Mitchel, Electrical Aaintenance Supervisor
- Mr. J. P. O'Hanlon, Unit Superintendent, Technical Support
Mr. V. Orlandi, IaC Lead Engineer
Mr. L. Noll, Shift Foreman
Mr. D. Pilsitz, Shift Foreman
Mr. W. E. Potts, Supervisor of Licensing
Mr. R. N. Prabhakar, Supervisor, Quality Assurance
Mr. W. J. Sawyer, Engineer-Senior I, Nuclear
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- Mr. M. A. Shatto, Engineer Associate III
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Mr. C. W. Smyth, Licensing Engineer
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2.
purpose and Scope of the Inweetion
I)
This report addresses two inspections.
Inspection 77-05, Unit 1,
was an announced inspection directed toward the review of plant
cperation activities and a review of the licensee's compliance to
s- fety limits, limiting systems settings, and limiting conditions
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for operations. The Unit 1 inspection also covered the followup
of previously identified unresolved items, items of noncompliance,
Inspection and Enforcement Bulletins, Circulars, and Licensee
event reports.
Inspection 77-09, Unit 2, was an announced inspection directed
toward the continued review of the quality assurance program for
station operations.
This inspection is based on 10 CFR 50, Appendix B Criteria, Section 17.2 of the FSAR, Quality Assurance Program for
Station Operations, and the implementing procedures.
The procedures
that implement FSAR Section 17.2 were reviewed to determine that the
procedures reflect compliance with regulatory requirements and the
licensee's commitments.
- Present at Unit 1 exit interview
1483 020
- Present at Unit 2 exit interview
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3.
Nonroutine Event Reports, Unit 1
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a.
Selected Reportable Occurrences were reviewed to verify that:
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The cause was identified and that details were clearly
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reported to the NRC and facility management;
Corrective action described in the licensae's report was
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taken to prevent recurrence;
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Each event was reviewed and evaluated as required by the
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Technical Specifications; and
Safety limits, limiting safety system settings, and limit-
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ing conditions for operation were not exceeded.
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This review included discussions with members of the plant
staff, inspection of PORC meeting minutes, internal site
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memoranda, physical observation of affected equipment, work
requests, and surveillance procedures.
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b.
The Rept. table Occurrences reviewed were:
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(1)
ER 76-40/3L, Abnormal Degradation of the Seal Ring in
DH-V1.
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(2)
ER 76-41/3L, Empty Fluid Reservoir of the Hydraulic Shock
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and Sway Suppressor located in Position RC-14.
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(3)
ER 77-01/1T, the "A"
Diesel Generator, DG, would not start
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in the event of an offsite power loss without an ES signal.
c.
The inspector's findings were acceptable except for those
Unresolved Items delineated below.
Also, inspection findings
relative to additional information concerning these events are
summarized, as appropriate.
(1) With respect to ER 76-40/3L:
On November 6,1976, the
body to bonnet seal ring on the Decay Heat Isolation
Valve, DH-VI, which had been leaking .2
.5 gpm, began
to leak excessively during a plant cooldown.
This valve
is normally closed during power operation and the increased
u
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leakage resulted when the valve was opened to provide
cooldown of the reactor coolant system.
The valve is not
isolable from the reactor coolant system and, therefore,
will require an extended shutdown to make permanent
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repairs.
The licensee chose to effect a temporary repair
until the next refueling outage.
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An engineering evaluation of the problem determined that
an acceptable repair could be made by drilling four
holes, 90 apart, through the valve body in the area of
the seal ring.
This would provide access to the thread
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relief area directly above the seal ring gasket and below
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the retaining ring. A commercial sealing compound,
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"Furmanite," would be injected through special adapters
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threaded into the drilled holes.
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The licensee engaged a consulting firm to evaluate this
method of repair.
The consultant performed a stress and
fatigue analysis of the effect caused by drilling the
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holes and found them to be acceptable within ASME Code
established criteria.
The consultant also suggested
that, as a result of the chemical analysis performed by
(])
the licensee showing a leachable chloride content of 50
l
<g
PPM and a total chloride content of 1300 - 1700 PPM, the
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nuclear steam system supplier (NSSS), Babcock and Wilcox,
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be consulted concerning the advisability of injecting
Furmanito. The concern was the increased potential for
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stress corrosion cracking (SCC).
The final recommendation
cf the consultant was to use the Furmanite.
The NSSS letter, dated November 4,1976, advised that,
due to the critical location of the valve and the relatively
high chloride content, they could not recommend the use
of Furmanite.
Concurrently, the licensee stated that the laboratory, on
running a blank sample to verify the chloride chemistry,
found the background contamination of chlorides to be 50
PPM.
Considering this, the laboratory felt that the
actual chloride content was approximately 5-8 PPM.
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The licensee's staff reviewed the various recommendations
and decided to use the Furmanite due to the reduced
chloride values reported by the laboratory and the other
positive factors such as:
(1) the known low operating
temperature of the valve,1400F; (2) the corrosion resis-
tant characteristics of 316 stainless steel; (3) the
low oxygen content of the reactor coolant water; and (4)
if the leak is completely stopped the area exposed to
water will provide very low quantitites of leachable
chlorides and no evaporating mechanism for concentrating
the chlorides, thus, minimizing SCC problems.
The staff
also recommended the following restrictions:
(a) The valve be repaired at the next refueling outage.
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(b) The valve (seal ring area) be completely sealed with
Furmanite so that leakage does not cause vapor con-
densation.
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(c) The temperature of the valve does not exceed 100 C
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and naterial temperatures are kept as far below that
{
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as possible.
([)
The procedure using the Furmanite repair method was approved
by the Plant Operation Review Committee on November 7,1976,
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and the leak was successfully repaired.
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The inspector rev tewed the above described repair program
and was informed by the licensee that plans are now being
made to leave the Furmanite repair in place beyond the
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next refueling outage for some extended period of time.
The licensee also stated that further engineering evalua-
tions are being incorporated into a report that is to be
issued within the next 2-3 weeks.
This item, 77-05-02, is considered unresolved pending the
NRC's review of the licensee's supplemental engineering
report and the valve repair schedule.
This review will be
completed prior to facility restart following the forth-
comina refueling outage.
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(2) With respect to ER 76-41/3L:
During routine surveillance
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of the snubber located inside the Reactor Building Secon-
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dary Shield wall, one snubber at position RC-14 on the
pressurizer spray line was found with an empty fluid
reservoir.
The inspector was shown the removed seals.
.
Discussions with licensee personnel indicated that the
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seals were damaged due to improper assembly. Also, one
seal was missing.
The action by the licensee is in agree-
ment with the Current Surveillance Procedure 1301-9.9,
Hydraulic Shock and Sway Suppressors, Revision 6, dated
July 15, 1976.
The procedure is performed to insure that
.
the hydraulic shock and spring suppressors used in safety
,
related systems are in proper operating condition.
The
procedure calls for surveillance to be increased as a
function of identified failed suppressors during a sur-
veillance.
The inspector has no further questions on this item.
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(3) With respect to ER 77-01/1T: On February 2, 1977, the
licensee determined that the "A" DG would not have suc-
Q
cessfully started in the event of a loss of Offsite Power
unless an ES signal was present.
The oil pressure low
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speed (OLPS) switch was found to be stuck. When the OPLS
!
switch failed to operate before the cranking timer operated,
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a start failure signal occurred that tripped off the DG.
If an ES signal is present this trip signal is defeated
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and the DG would have started.
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Diesel Generator "A" was tested and found operable on
February 1.
On February 2,1977, the "A"
DG was found
inoperable and it was concluded that the OPLS was or may
have been stuck for a period of time in excess of that
allowed by TS 3.7.2.c because DG "B" was tagged out for
maintenance.
The licensee will change the time setting requirements
once new OPLS switches are installed.
Procedure 1301-8.2
will be changed to reflect the new time settings.
This is an unresolved item (77-05-03) pending the comple-
tion of the corrective actions.
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4.
Seismic Qualification of Steam Generator Level and Pressure
Indications, Unit 1
References: NRC Inspection Reports 50-289/76-10, Detail s, para-
graph 6, 50-289/76-24, Details, paragraph 5.j , and licensee's
letter dated December 16, 1976 (GQL 1692.)
The inspector reviewed the Nonconformance Report No.76-362 which
identified 5 discrepancies with the Nonnuclear Instruments /Inte-
grated Control Systems (NNI/ICS) which were being modified to
upgrade their seismic classification (see reference reports.)
The inspector verified that all discrepancies had been addressed
by the engineering staff in a letter dated January 4,1977, and all
items were satisfactorily resolved.
The inspector had no further
questions.
5.
IE Bulletin / Circular Followup, Unit 1 (except where noted)
IE Bulletins /Circalars discussed below were reviewed to verify that:
!
Licensee management forwarded copies of the response to the
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bulletin / circular to appropriate onsite management representa-
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tives.
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,
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Information discussed in the licensee's reply was cupported by
--
,
facility records or by visual examination of the facility.
!
Corrective action taken was effected as described in the reply.
--
The licensee's reply was prompt and within the time period
--
described in the bulletin / circular.
The review included discussions with licensee personnel and obser-
vation and review of items discussed in the details below.
The licensee's actions and response concerning IE Bulletin / Circular
followup were acceptable.
Additional actions required by ta licen-
see are noted as unresolved items.
a.
Bulletin 76-06, Diaphragm Failure in Air Operated Auxiliary
Actuators for Safety / Relief Valves (IEB76-06).
References:
IE Bulletin, July 21, 1976; Licensee's Response dated July 30,
1976.
1483'025
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. . - .
-
.
. - . .
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.
i
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!
O)
15
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()
i
- ~
This kulletin deals with auxiliary air actuator diaphragms,
composed of dacron fabric reinforced silicone rubber, being
degraded.
The licensee's response indicated that there are no valves
which are considered to be in the category of safety related
diaphragm operated relief valves in high temperature systems.
The inspector discussed the design of the safety related
I
relief valves with the cognizant licensee engineer.
The
!
valves in use at TMI-1 are not insulated and operate by
mechanical linkage.
PORC minutes for PORC Meeting No. 345,
7/26-30/76 were reviewed.
The minutes indicated that the PORC
j
agrees with the negative response.
I
The iisspector has no further questions on this item.
!
j
b.
Circular 76-06, Stress Corrosion Cracks in Stagnant Low
Pressure Stainless Piping Containing Boric Acid Solution at
,
i
PWR's (IEC 76-06).
References:
IE Circular 76-06, November
24, 1 976; Licensee response dated December 29, 1976.
!
This circular deals w'ch through wall cracking that has occurred
in 304 stainless steel piping at PWR Nuclear Power Plants.
Similar failures were not found at TMI-1.
Th'e failures have
I)
been attributed to intergranular stress corrosion cracking
'
1
initiated on the inside wall of stainless steel piping.
The licensee was requested to describe their program to aseure
the integ ity of similar stainless steel piping.
i
,
The response by the licensee indicated that they have an ongo-
ing program of monitoring chloride levels in systems naving
similar characteristics of those having failures found at
other PWR's.
Current results indicated that chloride content
is less than 1 ppm in the following systems:
,
Decay Heat System
Borated Water Storage Tcnk
Reactor Coolant Bleed Tanks
Core Flood Tanks
Spent Fuel Pool
The inspector reviewed the Chemistry Log.
The following sur-
veillance data was recorded:
1483 026
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_.
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.
__
_
__
__
__.
._
!
- '
16
,
+
,
(l
Decay Heat System - for daily checks between November 14,
--
1976 through November 18, 1976, chloride ppm ranged from
0.09 to 0.30 ppm.
l
l
Borated Water Storage Tank - for November 13, 1976, not
--
i
detectable; December 13, 1976, not detectable.
Reactor Coolant Bleed Tanks - for November 16, 1976, B
--
Tank, 0.01 ppm; November 19, 1976, A Tank, not detectable;
November 20, 1976, B Tank, 0.08 ppm; November 21, 1976, C
Tank, 0.06 ppm.
iore Flood Tanks - for December 16, 1976, A Tank 0.05
--
ppm, B Tank 0.06 ppm; November 16, 1976, A and B Tank,
not detectable.
Spent Fuel Pool - for October 30, 1976, not detectable;
--
November 13, 1975, 0.06 ppm.
,
The licensee has stated that in the event chloride levels are
found to be at a threshold chloride value for stress corrosion
cracking (Reference:
Stress Corrosion Cracking of Iron-
()
Nickel-Chromium Alloys, R. M. Latanision and R. W. Staehle,
p
Ohio State University - publication,) special testing of the
piping involved will be considered.
-
The licensee will perform hydrostatic testing of the Reactor
Building Spray System in accordance with ASME Section XI
during the next refueling outage (scheduled to begin March 19,
1977.)
During the special test an ultrasonic examination will
be performed on the Reactor Building Spray piping.
At least 4
selected welds will be volumetrically examined in accordance
with ASME Section XI, Appt.' dix I, except that the examined
area will cover a distance of 6 times the pipe thickness but
not less than 2 inches nor more than 8 inches.
The special
test procedure will include the use of Surveillance Procedure
1300-IE, Revision 1, December 23, 1976, Manual Ultrasonic
Examination of Reactor Coolant and Associated Piping Welds.
1483 027
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/i
17
)
The special test procedure remains to be written and approved.
This is an unresolved item (77-05-04) pending the completion
of the procedure.
The IE Circular response transmitted by the licensee is cur-
rently being reviewed along with responses from other PWR
licenstes. A final decision on the adequacy of the response
bas not been made.
This is an unresolved item (77-06-13)
pending the final decision by NRC.
4
c.
Circular 76-05, Hydraulic Shock and Sway Suppressors - Mainten-
ance of Bleed and Lockup Velocities on ITT Grinnell's Model
Nos. - Figure 200 and Figure 201, Cutalog PH-74-R (IEC 76-05).
References:
IE Circular 76-05, Octouer 8, 1976; Licensee's
response dated January 5, 1977.
This circular deals with spectfic Suppressors and specifically
identified plants informed by ITT of a problem.
It further
'
requests the review by the licensee to assure that in the
,
event they have the identified suppressors that corrective
i
actions be performed.
l
O
The iicensee's response indicates enat the suspect suppressors
'
(
are not in use at TMI-1.
The inspector reviewed the licensee's
.
documentation listing the suppressors in use at TMI-l.
This
,
{
included Gilbert Associates - Snubber deal Replacement Matrix
for Three Mile Island Unit 1 and the Snubber History (WR 4438)
'
Fil e.
The same documents were reviewed by the licensee.
.
There was no indication that serial numbers B0001 through
'
B2000 are used at TMI-1.
This item was reviewed by PORC and documented in PORC Meeting
No. 367, December 27-30, 1976.
The inspector has no further questions on this item.
d.
Circular 77-01, Malfunction of Limitorque Valve Operators.
Reference:
IE Circular 77-01, January 6, 1977.
This circular requested that the licensee check his procedures
for proper precautions to be taken when closure of, torque
limit switch equipped valves are closed manually.
The pro-
cedures should address the following:
1483 028
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( I
Checks of operability following maintenance
--
Checks on manual closure
--
Personnel instructed to conform to procedures
--
Assure that bypass limit switch was not negated.
--
No response to this circular was required.
The inspector re-
viewed the actions taken by the licensee.
Procedure 1420-LTQ-2, Limitorque Operator, Limit Switch Adjust-
2
ment, Revision 0, April 2,1975, was reviewed.
The purpose of
this procedure is to provide instructions for the proper
settings of Limitorque Limit Switches.
Also, procedure 1420-
LTQ-3, Limitorque Saitch Adjustment, Revision 0, May 28,1975
,
was reviewed.
tieth procedures have been changed, reference
change requests Nos.77-058 and 77-059.
The changes include a check on the bypass limit switch, post
maintenance checks including dynamic checks to assure settings
l
are correct and the valve operable under operating conditions.
()
The procedure changes have been reviewed by PORC, reference
~
PORC Meeting 77-06.
Corrective action on the above procedures
i
apply to Unit 1 and 2.
The final revised procedures remain to be revised.
This item
'
77-05-05 is unresolved pending the final revision completion
of these procedures.
,
6.
Safety Limits, Limiting Safety System Settinos and Limiting Conditions
for Operation, Unit 1
a.
(1) TS 2.1.1 Reactor System Pressure and Temperature Limits,
as reflected in Figure 2.1-1 were reviewed for compliance.
Recorded data for the heat-up evolution attached to
0
operating procedure 1102-1, Plant Heat-Up to 525 F,
dated November 17, 1976 file, verify that the limits were
not exceeded.
1483 029
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19
(l
.
(2) TS 3.1.2.1 for heat-up were reviewed for the November
heat-up evolution.
The computer trend analog trace data
for temperature and pressure were reviewed.
The data as
plot' ?d on Figure 1, November 18, 1976, of operating
procedure 1102-1 were checked.
The heat-up rate was
within limits.
b.
Reactivity and Power Control
(1) TS 3.5.2.1, limits on the available shutdown margin, was
reviewed.
The filed recorded work sheet, November 19,
1976, was reviewed.
The worth determinations indicated
that the required limits were met.
(2) TS 3.5.2.5, control rod positions, was reviewed for the
2
period February 6-14, 1977.
Data is contained in Sur-
veillance Procedure 1302-1.4, Shift Daily Checks.
The
data was compared to TS Figure 3.5-2B.
The rod positions
were found to be within the required limits for the
period of operations reviewed.
i
c.
Power Conversion and Auxiliary Systems
(3
i ('
(1) TS 3.1.1.2 requires that one steam generator be operable
'
whenever the reactor coolant is above 250 F.
Operating
!
Procedure 1102-1, record for December 3,1976, and Sur-
veillance Test 1303-5.4, Emergency Feedwater Pumps were
reviewed. The Surveillance Procedure is performed to
verify that the turbine driven emergency feed pump (EF-
P1) and associated valves are operable in accordance with
TS 4.9 and to verify that the two motor driven emergency
'
feed pumps (EF-P2A and B) and associated valves are
operabl e.
The Surveillance Test 1303-5.4 contained a deficiency for
the test performed witn respect to valve EF-P2A.
D1scus-
sions with the Shift Foreman indicate that the valve was
manually operable and in the required open position.
(2) TS 3.4.6 requires all eighteen steam safety valves to be
operable; if r.ot a power penalty is imposed.
Verifica-
tion of steam safety valve operability is confirmed by
1483 030
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=
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20
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-
acceptable performance of Surveillance Test 1303-11.3,
'i
Main Steam Safety Valves, Revision 2, November 13, 1975.
!
The purpose of this procedure is to verify the setpoint
!
of the main steam safety valves, MSSV, MS-V-17A, B, C, D,
j
MS-V-18A, B , C , D, MS-V-19A, B , C , D, MS-V-20A , B , C , D ,
and MS-V-2'.A, B.
This test is performed to meet TS 4.1.2, Table 4.1-2, item 4.
,
Twenty five percent of the valves must be tested during
l
each refueling period.
The data of February 14,1976 was
reviewed. Valves MS-V-18A, MS-V-19A, MS-V-20A and MS-V-
j
21 A were tested satisfactorily.
l
d.
Containment Systems
(1) TS 3.6.4 requires that the reactor building pressure be
less than 2 psig and greater than 1 psig vacuum when the
plant is critical.
Surveillance procedure 1301-1, Shift and Daily Surveillance
Checks, Revision 2, dated April 17, 1974 was reviewed for
._
2/9,11,13,15, and 24/77.
The control room pressure
t.
meter was also checked on February 24, 1977.
The contain-
i()
ment pressure limits were found to be within limits.
(2) TS 3.6 applies to the containment integrity of the reactor
i
building.
Operating Procedure 1101-3, Reactor Building Integrity,
Revision 11, dated September 17, 1976 was reviewed for
+
November 18, 1976.
The procedure was completed and the
containment secured.
I
l
e.
Electrical Systems
'
(1) TS 3.7.1.e requires 25,000 gallons of fuel oil in the
storage tank prior to criticality.
The inspector visually inspected the control room indica-
tors. The panalarm was off indicating oil content above
the required minimum.
Procedure 1102-2 Three Mile Island
Plant Startup, records for December 3,1976 were reviewed.
The records indicate, step 28, that the required fuel was
available prior to criticality.
-
1483 031
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<1
.
(2) TS 3.7.1.f requires that the batteries are charged and in
service prior to criticality.
Procedures 1102-2, step
29, and surveillance procedure 1301-4.6, Station Storage
Batteries, Revision 2, dated September 10, 1975 were
reviewed. The purpose of the surveillance procedure is
to insure that the storage batteries are maintained in a
fully charged condition and also meet TS 4.6.2.b.
The
data sheet for January 7,1977 was reviewed and found
satisfactory.
f.
Emergency Core Cooling Systems
(1) TS 3.3.1.1.a requires that the Boric Acid Water Storage
tank contain a minimum of 350,000 gallons of 2,270 ppm
boron at a minimum of 400F prior to critical .
Procedure 1102-2 records for December 3,1976 were reviewed.
l
Step 7 verifies that TS 3.1.1.a was met. Baron concentration
of 2296 ppm, temperature 880F.
The inspector also noted
,
l
the control room readings for February 24, 1977.
The
!
indicators, DH3-LIl and LI2 indicated levels above the
l
minimum for the 350,000 gallons of solution in the tank.
s
'
()
I
(2) TS 3.3.1.2.c requires the Core Flood Tank discharge
(' )-
valves to be open prior to criticality and so indicated
on the control room ES panel .
Respective breakers for
4
these valves, CFV-1A and CFV-18, shall be open and marked.
I
The inspector reviewed procedure 1102-2 records for
December 3, 1976, step 20, page 39, for prior to critical
valve status.
Documentation indicated that the correct
positions of the valves were established.
The inspector
,
visually verified that on February 24, 1977 ES indication
showed the valves to be in the open position.
The breaker
panel, CES, in the Auxiliary Building was inspected.
The
breakers were found in the open position and marked with
tags no. 33 and 32 respectively.
The tags were checked
against the tag log and found to agree. The panalarm
indicator was out which also indicates the valves were in
the correct position.
The inspector noted that the ES
indicators for these two valves had yellow background and
were the exceptions for color coded recognition of required
position status. The licensee personnel know this as an
exception.
In the interest of minimizing error, the
licensee intends to review the reasons for this exception.
-
1483 032
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7
22
7.
Review of Plant Operations
a.
Shift Logs and Operating Records
The inspector reviewed records listed below, held discussions
with plant staff members, and inspected the control room on
February 24 and 25,1977.
(1) Shift and Daily Check: SP 1301-1 for the period February
1-15, 1977, and the Control Room Log Sheet for the period
of January 25 through February 13, 1977 were reviewed to
verify that:
(a)
Log sheets are completed properly;
'
(b)
Log sheet reviews are being conducted.
Findings were acceptable.
1
The inspector noted that the limits on the log sheet are
,
I
more stringent than required by TS.
This is acceptable;
,
I
however, when the limits on the log sheet are not met,
but are accepted on the broader basis, future problems
'
-
could result.
This kind of detail, to have the noted
criteria agree with the attainable and acceptable values,
4
was discussed with the licensee, and he agreed to look
'
into this potential problem area.
The content of the Shift and Daily Check was discussed
with the licensee, ami he agreed that consideration would
be given to includin; s'le TS reference and/or the spedfic
TS requirement for the parameter being recorded on the
check sheet.
.
These items will be reviewed during a subsequent inspection,
'
and the matter is designated as an Inspector Followup Item
(77-05-13.)
(2)
Primary Auxiliary Operators Log - Tour Readings: Entries
for the period January 25 through February 13, 1977 were
reviewed for completeness and details adequate to commun-
icate equipment status.
Findings were acceptable.
1483 ,033
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23
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_
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(3) Operating Orders:
The active SOP Book was reviewed and
it contained SOP's 453, 455, 456, 457, 458, 459, 461,
-
462, 263, 464, and 465.
No conflicts with TS require-
ments were observed,
b.
Tour of Accessible Areas
The inspector observed operations in the control room and
toured various levels of the Intermediate, Auxiliary and Tur-
bine Buildings and the Control Room Tower on February 24 and
25, 1977. The following observations were made and discussed
with plant staff members, as appropriate.
(1) Monitoring Instrumentation:
Control room indications
and/or records for BWST level, temperature and baron con-
centration, CFT pressure, level and boron concentration,
Sodium Hydroxide Tank and Sodium Thiosulfate Tank contents
and temperature, Control Rod Index, Nuclear Power Axial
Power Imbalance, Reactor Coolant flow, pressure and
.
outlet temperature. R& actor Building pressure, wind speed
l
and direction and River Water AT were examined, and no
discrepancies with Technical Specification LCO's were
'
)
-
observed. Additionally, Shutdown Panel ir.iications were
observed to be consistent with Control Room indications.
(2) Radiation Controls: Areas within the Auxiliary Building
were observed to be properly posted and controlled.
How-
ever, a problem area was identified.
Namely, there are
numerous individual roped off areas (Radiation and/or
Contamination Areas,) e.g. El 281', and entry into these
.
areas is controlled by a separate RWP. However, pro-
tective clothing (required by a RWP for each area) was
not readily available at each entry point.
This practice
required an operator to carry around several sets of pro-
tective clothing in order to enter those areas which
require an operational type inspection or surveillance,
or to perform an equipment operation.
The licensee agreed to evaluate this matter, and it is
designated as an Inspection Followup Item (77-05-14.)
.
1483 034'
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.
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24
(3)
Plant Housekeeping Conditions: Storage of mate'eial and
components ras observed with respect to prevention of
safety and f're hazards.
No adverse conditions of inmed-
iate safety cancern were identified; however, areas where
the need for b usekeeping improvements is indicated were
discussed with ilant and corporate management.
These
areas were ati. ibuted to a lack of administrative require-
ments, as discussed in Detail 9.k.
(4)
Existance of Fluid Leaks:
Fluid leaks observed had
already been identified by the licensee for future main-
tenance action.
(5)
Existance of Piping Vibrations: No excessive piping
vibrations were observed.
(6)
Eipe Hangers / Seismic Restraints: About 20 snubbers on
the Main Steam, Emergency Feedwater, and Reactor Building
spray systems were observed for proper fluid levels, 'nd
no adverse conditions were identified.
()
A partially filled plastic squeeze bottle of snubber
fluid was found at El 281' of the Auxiliary Building; the
bottle was not identified and was not controlled.
This
matter was discussed with the licensee, and he agreed to
establish procedural controls for snubber fluid and other
safety related consumable material, e.g., diesel generator
,
lube oil, lubricant, etc., as necessary, following with-
drawal of these items froin stores by plant personnel.
This item (77-05-06) is unresolved pending completion by
the licensee and review by a NRC:I inspector.
(7)
Valve Positions / Equipment Start Position Switches:
Valves DH-VISA, BS-V53A, BS-V49A, BS-V54A, BS-17A, BS-
178, BS-41B, BS-498, and BS-V548 were observed to be
locked open, and -valves DH-V38A and DH-V38B were observed
to be locked closed in accordance with procedural require-
ments.
Additionally, valves CF-VIA and CF-V1B were
observed to be open and red tagged in accordance with TS 3.3.1.2.c.
1483 035
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(8)
Equipment Caution / Lockout Tag Infctmation: The active
tag log was reviewed and the tagging associated with
valves CF-VIA and CF-V1B (#32 & 33,) RM-A6 (#1747,) and
a containment Building Emergency Ventilation Supply Fan
(#1745) was selected for further review.
No discrepancies
,
relative to approval and placement of tags were identified.
Additionally, the inspector observed the placement of tags
]
- 1745 and #1747 by shift personnel.
1
(9) Plant Tour: The licensee's administrative policy and
'
practice regarding plant tours conducted by the Unit
Superintendent and the duty Shift Supervisor were deter-
.
mined. Although there are no administrative requirements
'
!
in this area, the inspector determined by discussions with
these individuals that plant tours are made by the Shift
- ,
Supervisor at least once per shift and by the Unit Superin-
tendent as often as possible consistent with his work load.
(10)
Control Room Manning: The inspector observed that the
day and swing shifts were staffed and the Control Room
was manned in accordance with TS 6.2.2 and 10 CFR 50.54(k).
l
i
'
(11) Maintenance Item: The ir.spector observed maintenance per-
sonnel working on the valve operators of MS-V10A and MS-
i108. The personnel were using an approved Work Request
!
(WR 19011,) the maintenance foreman was present, and the
Shift Supervisor was aware of this maintenance task. The
'
inspector had no further questions on this matter.
i
(12)
Jumper Control: The inspector observed that a Jumper (#20)
was installed in Junction Box T661 between terminals 17D
and 200.
This was discussed with the duty Shift Supervisor,
who was aware of the jumper installation. A subsequent
review of the Jumper Log revealed the jumper had been
installed and was being controlled in accordance with
AP 1013.
The inspector had no further questions on this
matter.
8.
Corrective Action for pt eviously Identified Enforcement Items
a.
Item 76-11 (Detail 3)
The licensee's actions for this item were described in Met Ed
letters dated June 21,1976 (GQL 0882,) September 30, 1976
(GQL 1372,) and Noverr'er 12,1976 (GQL 1579,) and these actions
]
were to be completed tey November 24, 1976.
1483 036
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!
26
-
Based on review of the PORC closecut form for this item, PCR
76-532 and related review comments from the Manager, Operational
Quality Assurance (M0QA ) and discussions with plant personnel,
the inspector determined that the licensee's comitments, as
stated in the referenced correspondence, had not been completed
as of February 25, 1977.
PCR 76-532, which affects AP 1001,
had been reviewed by the Unit 1 PORC and the Unit 2 PORC, had
been approved by the Unit 1 Superintendent and the Unit 2
Superintendent, and had been sent to the Corporate Office on
October 12, 1976 for approval by the Manager, Operational
Quality Assurance, M0QA.
Following review by the M00A, PCR
,76-532 was returned to the site on October 28,1976 for
resolution of the M00A's comments.
The status of PCR 76-532
,
had remained unchanged since that time.
Completion of the licensee's corrective action will be reviewed
during a subsequent inspection, and this item (77-05-07) is
unresolved.
!
b.
Item 76-19-2
i
The licensee's actions for this item were described in a Met
t
)
Ed letter dated September 21, 1976 (GQL 1318,) and these
actions were to be completed on August 27, 1976 and November
,
1
1, 1976.
Based on review of the PORC Closeout Form for this item, NCR
76-372, and discussions with plant personnel, the inspector
determined that the licensee's commitments, as stated in the
referenced correspondence, had been completed for the August
27, 1976 action item, but had not been completed for the
November 1,1976 action item as of February 25, 1977.
Docu-
mentation of the training of Mechanical Maintenance personr.el
could not be located, but the inspector was informed that this
training had been completed by November 1,1976.
Training of
I&C and Electrical Maintenance personnel had not been completed
according to plant personnel, and that the documentation of
those personnel who had completed the training was stili in
circulation within the respective groups.
Completion of the licensee's corrective action will be reviewed
during a subsequent inspectf x , and this item (77-05-08) is
unresolved.
_
1483 017
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.-.
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.
.
27
The licensee's failure to take corrective action in accord-
ance
-
bis commitments to NRC:I, as described in subpara-
' ra n...
L c .
b, is contrary to the requirements of 10 CFR 50,
,
' pendi. D,
riterion XVI and the accepted Operational Quality
.
Assurance Plan (FSAR Section IA) Section 6.7.
This Item of
' .ncompliance (77-05-08) is an Infraction.
c.
Item 76-25-1
In his response letter dated Decembe; 8,1976, the licensee
documented corrective actions for this item which was identified
in enforcement correspondence to the licensee dated November
'
18, 1976.
The inspector reviewed the licensee's records for
fire extinguisher inspections conducted in December 1976 and
January and February 1977.
This inspection assignment was with
the Mechanical Maintenance Department at the time of the inspec-
tion although the licensee's response had indicated that the
inspection duties might be reassigned to the TMI Safety Super-
visor.
The inspector had no further questions.
9.
Previously Reported Unresolved /Other Items
\\
l.
a.
GORB Review of TS and License Violations
Reference: NRC:I Inspection Reports 50-289/76-01, Detail
13.b.(8) and 50-289/76-17, Detail II.11.
Based on review of GORB Meeting Minutes (Draft) for Meeting
No. 25 conducted on December 8-9, 1976, the inspector deter-
mined that the Items of Noncompliance delineated in NRC:I
Inspection Reports 50-289/75- 01, 04, 06, 08, 13, 14, 15, 20,
and 23 had been reviewed.
This item is resolved.
b.
Radiation Chemistry Technician Training on Procedure HP 1631
Reference: NRC:I Inspection Report 50-289/76-10, Detail
3.b.(1)(b).
1483 038
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28
Based on review of training records maintained by the Acting
Supervisor of Radiation Protection and Chemistry, the' inspector
determined that the 18 technicians had received training on
Procedure HP 1631. Additionally, this procedure had been
revised (Revision 1, dated December 16,1976) to provide a
detailed checklist covering operations.
This item is resolved.
c.
GORB Review of TS and License Violations
Reference: NRC:I Inspection Report 50-289/76-10, Detail 8.b.(4)
and 50-289/76-17, Detail II.10.d.
Based on review of GORB Meeting Minutes (Draft) for Meeting
No. 25 conducted on December 8-9, 1976, the inspector determined
that the Items of Noncompliance delineated in NRC:I Inspection
Reports 50-289/76-02, 03, 11, 13, 15, 16, 17, 18, 19, 20, 21,
and 24 had been reviewed; however, the 3 Items of Noncompliance
delineated in NRC:I Inspection 50-289/76-03 had not been reviewed,
and these items will be reviewed in the next GORB Meeting)(Sche-
duled for March,1977.)
This item (redesignated 77-05-09
remains unresolved.
'
d.
Reactor Building Purge System
Reference: NRC:I Inspection Report 50-289/76-15, Detail 21.
,
Based on review of procedures RP 1501-1 (Revision 2 ) RP 1501-2
(Revision 1,) and SP 1303-10.1 (Revision 3,) the inspector
determined that the subject procedures had been revised in
accordance with TS requirements on January 14, 1977 to include
those items previously identified by a NRC:I inspector.
This item is resolved.
e.
Record Storage Inadecuacies
Reference: NRC:I Inspection Report 50-289/75-14, Detail 12.b.
Detail 12.b of the referenced Report identified an Unresolved
Item with respect to licensee action to correct record storage
inadequacies which had been identified in the Chemistry, Health
Physics, and Operations Departments during the licensee's con-
duct of his audit 75-10.
These specific inadequacies had been
corrected.
The item is resolved.
1483 039
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._.
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$
29
However, in review of the corrective action on this audit
(75-10,) the inspector identified that finding number 2
remained uncorrected as of February 25, 1977.
This finding,
which documented a failure to review records prior to storage,
was first given a due date for completi
of June 15, 1975.
This date was subsequently extended to July 30, 1976; October
30, 1976; and most recently to January 15, 1977.
The licensee's
grarting of numerous extensions was the subject of Unresolved
Item 75-24-12 (see below.)
The action for an overdue commit-
.
ment date based on the January 15, 1977 date has not yet been
,
required based on the licensee's approved precedure.
The
completion of corrective action for Unresolved Item 76-24-12
should prevent recurrence of this number of extensions.
The
licensee's procedure for overdue commitments should resolve
this finding if followed.
Until Finding 2 of Audit 75-10 is closed, this item (77-05-10)
is unresolved.
The following, Previously Reported Unresolved Items,
--
were recorded in NRC:I Inspection Report 50-289/76-24:
l
O
f.
Item 76-24-2, FSAR Change for RCP Monitor Delay Time
Based on review of Revision 2 to the FSAR dated January 28, 1977,
as posted in Controlled Copy No. 9, the inspector determined
i
that page 14-66a of the FSAR had been revised to include the
new B&W analysis.
i
l
This item is resolved.
g.
Item 76-24-3, Additional Evaluation of ER 76-18/1T
Based on review of the licensee's evaluation (GEM 3443 and
PORC Meeting Minutes,) the inspector determined that the
analysis documented in ER 76-18/1T used the correct fuel den-
sification penalty.
This item is resolved.
1483 040
~
.
G
_.
.
.-
-.
.-
..- - - -.
_
- . . . . .
-
.
.
,
30
h.
Item 76-24-4, Repair of Valve MU-V2B
Based on review of completed Work Request WR 15772 (Signed
off on December 7,1976) and discussions with plant personnel,
~
the inspector detennined that the valve operator had been
repaired, the valve had been satisfactorily tested, and that
no recurrent problems had been experienced.
This item is resolved.
i.
Item 76-24-5, Long Term Corrective Action for ER 76-28/4___T
and 76-35/lT
Based on review of Interoffice memoranda (GQM 3225, dated
i
November 1,1976, and GNM 3280, dated November 8,1976),
discussions with plant personnel and observations of Control
'
Room indicators, the inspector determined that the licensee
had established and implemented new guidance concerning
control of the river water discharge temperature which pro-
j
vided more operational flexibility while complying with re-
quirements and that no recurrent problems had been experienced.
!
()
This item is resolved.
'
j.
Item 76-24-10, GORB Review of Reportable Occurrences
j
Based on review of GORB Meeting Minutes (Draft) for Meeting
No. 25 conducted on December 8-9, 1976, the inspector deter-
,
!
mined that ER 76-16/3L, ER 76-26/3L, ER 76-30/3L, and ER
76-31/3L, as well as numerous other event reports, had been
'
revie'ed.
This item is resolved.
k.
Item 76-24-11, Housekeeping Procedure
Based on review of NCR 76-386, which tracks
1 findings of
QC Surveillance Report 76-192, discussions -
.. lant per-
sonnel and observations of housekeeping condicions, the
inspector determined that the licensee's corrective action to
achieve compliance with ANSI N45.2.3 was in progress, but not
1483 041
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_ - .
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.
%
31
-
yet completed, i.e., the housekeeping procedure had been
reviewed by the PORC on two occasions, and there were still
major comments to be resolved.
The commitment date to resolve
the NCR had been extended from December 1,1976, to March 1,
1977, in accordonce with the established QA procedure; however,
the Unit 1 Superintendent informed the inspector that the
March 1,1977, date would not be met due to the workload
involved with the refueling outage (scheduled to begin March
19, 1977) and the work necessary to integrate the housekeeping
requirements into the same procedures being developed for Fire
Prevention / Protection.
To resolve this matter in the interim and for the long term,
the Unit 1 Superintendent made the following commitments to
NRC:I during the exit interview:
(1) 3y March 5,1977, written administrative controls would
be established to designate all no smoking areas and all
areas where control of combustible material is required.
I
(2) Management attention would be focused on present house-
j
keeping conditions and practices to achieve improvements
-,
!
()
on a continuing basis while development / approval of the
!
~
housekeeping procedure progressed.
'
(3) By April 15, 1977, the administrative procedure governing
housekeeping activities would be approved and in use.
This item remains unresolved and is designated as item 77-05-
11 for future inspection followup.
1.
Item 76-24-12, Revision of Procedure GP 4015 to Include
Criteria on Due Date Extensions
Procedure GP-4015, Revision 3, dated December 27,197.6, now
includes specific criteria on granting extensions when an
established audit finding corrective action completion date
can not be met.
This item is resolved.
1493 042
.
- - _ .
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-
,,--~~me
-,e.---~-n_,-
- - - -
_
_
- - -
. - .
.
. .
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32
s
l
.
m.
Item 76-24-13, Revise Procedure GP 4015 to Include
Criteria on Closecut
Precedure GP 4015, Revision 3, dated December 27, 1976,
now includes specific guidance on verification of comple-
tion of corrective action on audit findings before listing
the finding as closed.
i
This item is resolved.
I
n.
Item 76-24-14, Verify that Audit Report 75-32 is Available
i
at Site QC Files
!
l
Audit Report 75-32 was available in the site QC files as
required.
,
!
This item is resolved.
i
o.
Item 76-24 J15, Revise GP 4407 to Designate Duplicate OC
Record Storage Requirements
Procedure GP 4407, Revision 1, dated January 13,1977, now
'
( ,/
,
i
includes designation of duplicate record storage require-
,
-
ments and locations.
'
This item is resolved.
p.
Item 76-24-16, Revise Procedure AP 1016 to Specify How
Modifications are Sent to Training
1
I
Procedure AP 1016 has been revised to document the current
methods used to notify training personnel when completed
modifications are to be included in the training program.
This procedure has been under review by the PORC since
November 1,1976.
During the referenced inspection, the
licensee had stated that this procedure would be revised
by January 3,1977.
During the exit interviews the inspec-
tors discussed the desireability of meeting commitment
dates documented in NRC reports.
The Unit 1 Superintendent
stated that commitment dates were given with the full in-
tention to have actions ccmpleted as stated.
The Manager
of Quality Assurance stated that only commitments documented
1483 043
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33
in official correspondence to the Commission were considered
to be binding.
The inspectors stated that commitments docu-
mented in the inspection reports were considered as goals
to be met.
However, the inspectors stated that dates which
are considered as more than goals would be set out in the
letters which transmit the inspection reports.
Item 76-24-16 remains unresolved and is designated as item
77-05-01 for future inspection followup.
q.
Item 76-24-17, Verify Completion of Corrective Action on
NCR TMI-76-439
Procedure GP 4003, Revision 2, dated February 21,1977, re-
solved NCR TMI-76-439 by including the ANSI N45.2.6 quali-
fication requirements.
This item is resolved; however, as
with item 76-24-16, the date stated in the referenced report
for completion of this item was January 3,1977.
This item
-
was also referenced during the exit interviews as discussed
under item 76-24-16 above.
,
!
This item is resolved.
,
r.
CTSS Review of Facility Procehre Changas
Reference: NRC:I Inspection Report Numbers 50-289/76-01,
Detail 14.c. , 50-289/76-10, Detail 13.a, and
50-289/76-17 Detail II.10.a.
Based on review of the PCR Status Log and discussions with
a corporate staff member, the inspector determined the
current status of the PCR's covering 1974,1975,1976 and
1977, was as follows:
(1)
For 1974, of the 514 PCR's generated, 499 had been
reviewed,13 had been assigned for review, and the
remaining 2 had not been assigned.
(2)
For 1975, of the 544 PCR's generated, S20 had been
reviewed,19 had been assigned for review, and the
remaining 5 had not been assigned.
1483 044
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_.
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_ _ __
_
_
_
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. - -.--_-..- - -
.
34
!
C;
.
(3) For 1976, of the 831 PCR's gene:ated, 785 had been
reviewed,11 had been assigned for review, and the
remaining 35 had not been assigned.
(4) For 1977, of the 78 PCR's generated, 55 had been
reviewed, 13 had been assigned for review, and the
remaining 10 had not been assigned.
'
(5) The remaining 24 PCR's from the 1974-1975 backlog
which were deemed to have a significant affect on plant
operations had been reviewed.
The licensee is continuing to meet the comitments made to
NRC:I.
This matter will continue to be reviewed during sub-
sequent inspections, and it is designated as an Inspector
Followup Item No. 77-05-12.
10.
Procurement Control - Unit 2
a.
Administrative Controls
The inspector verified that the licensee has administrative
controls that equire procurement documents for safety-re-
lated items to provide for the following:
'
._
l
(1) Specific identification of equipment;
j
(2)
Identification of any test, inspection and acceptance
-
requirements;
(3) Raquisite technical requirements;
(4) Access to the supplier's plant or records;
(5) Requisite documentation to certify the item being
procured (Certificate of Conformance); and
(6) Contractor / supplier QA program.
1483 045
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The following procedures were reviewed for verification of
the above. Where verification was lacking it is so noted
as an unresolved item.
GP 1009, Revision 0, Procedure Document Control
GP 4005, Revision 1. Review of Procurement Documents
As e result of the above review, the following unresolved
item was identified:
i
77-09-02, With respect to the use of a Certificate of Con-
formance, in lieu of original records, ANSI M45.2.13, Section
10.2 requires that certain minimum documentation should be
supplied such as:
specific identification of purchased item;
--
the specific codes, standards or other specifications
--
,
met by the purchased item;
i
!
the identification of procurement requirements that
-m
--
!
have not been met; and
'
attestation by a person responsible for the supplier
--
QA function.
The licensee's procedures do not address the above minimum
documentation criteria for Certificates of Conformance.
b.
Procurement Measures and Responsibilities
The inspector verified that the licensee has administrative
controls that provide measures and assign responsibilities
in writing for:
(1)
Initiation of procurement documents;
(2) Review and approval of specifications differing from
original design documents;
1483 046
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36
t
(3)
Review and approval of procurement documents;
(4) Basis for designation of quality classification of pro-
curement items.
The following procedures were reviewed for verification of-
the above:
Gp 2009. Revision 0. Procuremetit Document Control.
--
,
GP 1011, Revision 1, Preparation, Charging, Updating,
--
and Issuance of Specifications and Bills of Material.
'
i
GP 4005, Revision 1, Review of Procurement Documents.
--
I
c.
Bidders / Suppliers
The licensee's procedures were reviewed to verify that adminis-
l
trative centrols provide for the following concerning bidders /
!
suppliers:
(
j
(1)
An acceptable method is established for " qualifying"
suppliers;
'
I
(2)
Provision for purchaser's right of access to supplier's
facilities and documents;
(3)
Maintenance of an " approved bidders" list;
.
(4) Maintenance of records of supplier qualification and audit.
The following procedures were reviewed for verification of
the above:
GP 0013, Revision 1, Evaluation and Qualification of Ven-
--
ders and Contractors.
GP 1016, Revision 0, Vendor Evaluation and Selection.
--
GP 4010, Revision 1, Approved Vendors List.
--
.
.
1483 0-4i7-
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. . . .
. -..
--.m._
-_.
-
,
/
!
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/
37
9
)
11.
Receipt, Storage, and Handling, Unit 2
a.
Receipt Inspection
The licensee's procedures were reviewed to verify that admin-
istrative controls provide for the following concerning receipt
inspection of safety related items:
(1) Written requirements for conducting receipt inspections;
(2)
Requirements for receipt inspection of shipping damage;
(3)
Requirement that supplies will be examined for conformance
with requirements specified on original procurement docu-
ment;
,
'
(4)
Requirement that documentation of the receipt inspection
be prepared and retained.
i
The following procedures were reviewed for verifications of
the above:
e
o
)
GP 1009, Revision 0, Procurement Document. Control.
--
'
GP 4008, Revision 2, Receipt Inspection of Material and
--
Equipment.
b.
Disposition of Items
The licensee's procedures were reviewed to verify that the
following administrative controls provide for disposition of
items received onsite:
.
(1) Acceptable items including:
(a) Tagging / marking for storage;
(b)
Immediate issue for use.
(2) Nonconforming items including:
(a)
Marking and segregating;
(b)
Prohibiting the use of items in a " nonconforming"
status;
1483 048
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_ . .
.-
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...
-- -.
-
-
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38
(c) Notifying affected organizations of nonconforming
items;
(d)
Documentation requirements.
(3)
Conditional release items including:
(a)
Justification for use;
(b)
Documentation required;
(c) Authority for conditional release of item.
The following procedures were reviewed for verification of
the above:
'
FSAR Section 17.2.12, Control of Purchased Material, Equip-
--
ment, and Services.
I
j
GP 4008, Revision 2, Receipt Inspection of Material and
--
-
Equipnent.
'
( 'l
AP 1018, Revision 2, Quality Control Warehousing.
-
--
,
c.
Storage
Stores Procedure No. 4, Material Storage, was reviewed to
verify that controls have been established for the following:
(1)
Levels of storage and appropriate environmental conditions;
(2) Storage controls including access, identification of items,
coverings, and preservatives;
(3)
Requirement to conduct periodic inspections of the storage
area;
(4) Maintenance and care of items in storage, including shelf
life.
1483 049
s
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es-
p.
e
-p gy.y
e se
es.w ees-
N
-we
. = * - .
mwe+
--ee--
.
.
39
,
-
I
d.
Material Handling
The licensee's procedures were r .iewed to verify that the
i
following administrative controls provide for handling safety
related material:
(1)
Routine and special handling measures are specified;
(2) Hoisting equipment controls are established.
The following procedures were reviewed for verification of the
above:
Stores Procedure No. 4 Material Storage.
--
,
FSAR Section 17.2.18 Handling, Storage, and Shipping.
--
12. Tests and Experiments, Unit 2
The inspector verified, by a review of Sections 6.1.1.a and 6.9 of
the Techn! cal Specifications, that the licensee has established
.
y
controls for the following:
.'"
>
a.
The handling of requests or proposals for conducting plant
.
tests or experiments involving safety related cornponents,
systems or structures or modes of operation different from
'
those described in the FSAR.
b.
To assure that all tests and experiments will be performed in
accordance with approved written procedures.
c.
To assure that responsibilities have been assigned for review-
ing and approving test and experimental procedures.
d.
To assure that all proposed tests and experiments will be
reviewed to determine whether they are described in the FSAR.
e.
To assure that respensibilites have been assigned to assure
that a written safet/ evaluation pursuant to 10 CFR 50.59,
will be developed for each test or experiment not described in
the FSAR to assure that it does not involve an unreviewed
safety question or enange in the Technical Specifications.
1483 050
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_.%,.
.
. mw pp eg
+
-w
-es-
w+-
.__
-._
_
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- - . - .
...
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' >
40
13.
Design Changes, Unit 2
Temporary Modifications Lifted Leads and Jumpers
The licensee's procedures were reviewed to verify that controls
have been established for:
a.
The review and approval of temporary modifications in accord-
ance with Section 6 of the Technical Specifications and 10
CFR 50.59.
b.
The use of detailed approved procedures when performing tem-
parary modifications.
c.
The assignment of responsibility for approving procedures in
(b) above.
d.
The maintenance of a formal record of the status of temporary
,
j
modification, lifted leads and jumpers, temporary strainers,
i
and temporary trip points of control equipment.
!
s
(-)
e.
Independent verification where appropriate of installation and
-
removal of temporary modifications, lifted leads and jumpers.
f.
Functional testing of equipment following installation or
removal of temporary modifications,
g.
Periodic review of lifted leads and jumper records.
The following procedures were rev1w d for verification of the
findings above:
AP 1013, Revision 3, Bypass of Safety Functions and Jumper
--
Control.
GP 1003, Revision 2, Control of Design Changes / Modifications.
--
GP 4004, Revision 0, Review of Design Specifications and
--
Requirements.
1483 051
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._
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. _ _
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-.~y
- - - - - .
.
._
_
_.
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'
.
!
')
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41
4
14.
Maintenance, Unit 2
i
Housekeeping Controls
The licensee's procedures were reviewed to verify that the follow-
ing housekeeping controls and responsibilities have been established
which include:
a.
Establishment of Housekeeping Zones,
b..
Control of housekeeping during work activities.
Section 2.1 of ANSI N 45.2.3 - 1973 requires the control of house-
keeping during work activities and the establishment of housekeeping
zones.
The licensee's procedures do not address housekeeping zones
or the control of housekeeping during work activities.
The licensee
identified this item under Nonconformance Report (NCR)76-386, and
is currently preparing Station Administration Procedure No.1020
which addresses Housekeeping.
Until the required procedure has
l
been reviewed, approved, and issued, this is an unresolved item
(77-09-03.)
l
. '
.
,
'
'
15.
Surveillance Testing and Calibration, Unit 2
The inspector verified that the licensee has administrative controls
that require:
a.
Calibration requirements for components associated with safety
related systems or functions but which are not specified in
the technical specifications as requiring calibration.
b.
Assignment of responsibility in writing to maintain the " master
calibration schedule" up-to-date.
c.
Performing component calibrations in accordance with approved
procedures which include acceptance criteria.
d.
Assuring that required component calibration schedules are
satisfied.
The following procedures were reviewed for verification of the
findings above:
,
,
'
4
1483 052
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.
42
<
AP 1016, Revision 9. Implementation and Control of Station
--
Maintenance and Modifications.
GP 1003, Revision 2, Control of Design Changes / Modifications.
--
IC. TMI Unit 2 OA Systems List
TMI Unit 1 components, systems, and structures within the scope of
the Met Ed Quality Assurance Plan are listed in the Appendix to
Procedure GP 1008, Revision 1, Quality Assurance Systems List, and
include consumable items such as Boric Acid, Sodium Hydroxide, and
Sodium Thiosulfate.
TMI Unit 2 components, systems, and structures within the scope of
the Met Ed Quality Assurance Plan are currently determined in
'
accordance with Burns and Roe Standard Procedure SP-88.
This list
does not include consumable items such as Boric Acid, Sodium Hydroxide,
etc. The licensee stated that a new QA Systems List for TMI 2 was
under development and would be similar to the TMI 1 list, including
the listing of consumable items.
Until the new QA Systems List for
TMI 2 is approved and issued, this is an unresolved item (77-09-
04.)
-
17.
Preoperational Test Records, Unit 2
a.
Programatic Controls
The licensee has established, through his representatives
GPUSC and UE&C, programatic controls for records created
during the preoperational testing phase.
These records are
controlled as quality assurance records only after they are
completed in accordance with the definition of quality assurance
records as stated in ANSI N 45.2.9, Paragraph 1.4.
Where
applicable, the program defines the controls required by ANSI
N 45.2.9 for the records created during this phase of operations.
Following completion and review, most records a.e turned over
to the licensee so that retention periods are controlled under
the licensee's Quality Assurance Program for Operations rather
than by the Startup and Testing Quality Assurance Program.
The retention /retrievability of records of the Preoperational
Phase is checked by the routine inspections conducted after
issuance of the Operating License.
The inspector iJentified no discrepancies.
1483 053
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43
b.
Records Selected
The inspector selected and reviewed the records listed below
to assure that the programatic controls were used.
The records
were selected to give coverage over a large period of time and
over different stages of record completion and to cover records
of both licensee representative organizations.
Records reviewed
were:
Problem Reports (for Unit 2, numbers started with 2001)
2001 - Decay Heat (BWST) dated July 7,1974
.
--
2050 - Integrated Control System dated June 15, 1976
--
2101 - Integrated Control System dated December 6, 1976
--
2130 - Reactor Protection System dated February 23, 1977
--
Turnover Packages (MTX File)
5.2 - Auxiliary Building Sump Pumps - Electrical
--
,
51.1 - Diesel Generator Air System-Instrument Calibration
--
75.3 - Fire Protection System, Pressure
--
113.3 - OTSG - Chemical Cleaning
--
Preoperational Tests
SP 204/4, Reactor Building Spray Nozzle Air Test dated
--
November 8, 1974
TP 235/5, Circulating Water Pump House dated February 10,
--
1975
TP 235/6, Containment Building Area 3 ump Test dated
--
December 20, 1976
These records were reviewed only for application of program
controls, not for record content / acceptability.
..
1483 054
z
e
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-.-
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-
.
.
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44
,
!
l
c.
Observation
,
The inspector observed evidence of a rodent infestation prob-
lem, such as chewed telephone cables, in the areas outside and
under the trailers where records are stored.
Completed records
were stored in fire resistant file cabinets and the inspector
found no evidence of rodent damage on the records reviewed.
The licensee's representative was aware of the problem but
stated that rodents had been limited to areas outside of the
interior of the trailers.
~
The inspector had no further questions at this time.
18. Startup and Test Quality Assurance Program, Unit 2
4
'
The description and controls for this program were reviewed and
,
documented in Report 50-320/76-05. At that time, February 23-25,
1976, audit and inspection activities had not been completed under
the aegis of this program.
Since these activities required review
for acceptability, two followup items (76-05-04 and 76-05-05) were
documented.
These areas were reviewed with results as indicated
()
below.
I
a.
Audits
The licensee's representative, GPUSC, had conducted three
audits during the period from April 1,1976 through January
31, 1977.
During these audits, thirty-one items requiring
followup were identified. The audits reviewed, areas covered,
-
l
and dates conducted are listed below:
76-08, Startup and Test Program Activities, conducted
.
--
April 1 to May 6, 1976;
76-12, Startup and Test Program Organization, conducted
--
June 22-24, 1976; and,
77-01, Jurisdiction and Tagging of Equipment, corducted
--
January 31, 1977.
Apparent gaps in the numbers were filled with audits of con-
struction activities which are conducted by the same group
under the Construction Quality Assurance Program.
Audit 77-01
was issued February 17, 1977, 3 working days prior to this
.
%w'
1483 055
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. _ . .
.-
.
--
..
,
.
(}
45
inspection, and answers /corre<.tive actions K u e therefore not
available for review. The licensee had identified 23 items,
i
22 which required answers / corrective actions, during the con-
'
I
duct of audits 76-08 and 76-12. The inspector found that 2
of these items, Findings 4 and 8 of Audit 76-12, had not been
'
answered nor had corrective actions been completed as of
February 24, 1977. These items had been identified to the
-
i
audited organizations during the audit conducted June 22-24,
1976 and were officially documented in a letter dated July 12,
1976, which forwarded ccpies of the audit and audit tindings.
j
In answer to the inspector's question, the licensee's represen-
l
tative stated that no measures had been established and docu-
l
mented to assure that conditions adverse to quality identified
during audits would be corrected as soon as practicable.
i
i
'
10 CFR 50, Appendix B, Criterion .iVI states in part: " Measures
shall be established to assure that conditions adverse to
quality.. . . are promptly identified and corrected . . . ."
The accepted Quality Assurance Program for Startup and Testing
(FSAR Section 17.3,) Section 17.3.2, item 3 states in part:
,
( >'-
" ANSI N 45.2 will be complied with . . . ." ANSI N 45.2,
,
Section 17 states in part: " Measures shall be established
i.
-
i
and documented to assure that conditions adverse to quality
h
. . . are promptly identified and corrected as soon as prac-
ticabl e . . . ."
The failure to establish and document measures to assure that
.
conditions adverse to quality will be corrected and the failure
l
to correct 2 of the 22 conditions requiring corrections as
l
soon as practicable collectively constitutes an Infraction
level Item of Noncompliance (77-09-01.)
'
l
Followup Item 76-05-05 is closed.
b.
Inspections
The licensee's representatives, GPUSC and UE&C, had conducted
inspections of activities under the Startup and Testing QA
Program since the previous inspection.
A sample of these
inspection reports were reviewed.
The reports reviewed,
area (s) covered, and dates conducted are listed below:
14831056
.
. . . _ . . . , _ . . _ . _ _ _
.
. . _ _ _ _ . _ . _ . _ _
_ _ . _ . . . _ _ . ,
_ _ _ . , _ ,
._
.
. -_.
--.
-
- - - . - ---
_.
. - -
- . .
'
.
.
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46
'
l
P-3307, Electrical Circuits, January 12, 1977
--
P-3143, Punch List Items, July 8, 1976
--
P-3336, Electrical Circuits, February 18, 1977
--
P-3335, Flange Studs, February 17, 1977
--
P-3290, Terminations, December 30, 1976
l
--
l
P-3291, Terminations, January 3, 1977
--
'
P-3088, Rectifier EEJ-2-2a, February 24, 1976
--
P-3162, Rectifier EEJ-2-2a, August 17, 1976
--
P-3331, Main Steam Punchlist, February 7,1977
--
'
P-3343, Main Steam Hydro, February 21, 1977
--
P-3344, OTSG Hydro, February 21, 1977
--
.
!
The inspector selected approximately 10% of the issued reports
!
for review to assure that documentation, followup, and close-
out controls specified in the licensee's program were carried
out.
,
The inspector identified no discrepancies.
'
Followup Item 76-05-04 is closed.
19.
Unit 1/ Unit 2 Interface Ite_m
During discussions with plant personnel, the inspector learned
,
that extraction steam from the Unit I turbine had been exported to
Unit 2 to allow preoperational testing of its secondary systems.
Based on further discussions with plant personnel and review of
procedures, the inspector determined that the steam had been
exported and the condensate returned in accordance with approved
Unit 1 procedures.
Additionally, the Unit 1 Emergency Procedure
for responding to Steam Generator tube leakage had been revised to
1.483.057
-
/
.
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