IR 05000289/1974018
| ML19253B757 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/09/1974 |
| From: | Davis A, Spessard R, Streeter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19253B756 | List: |
| References | |
| 50-289-74-18, NUDOCS 7910180748 | |
| Download: ML19253B757 (28) | |
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U. S. ATOMIC ENERGY CO:OilSSION
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7IRECTORATE OF REGUL\\ TORY OPERATIONS
REGION I
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RO Inspection Report No:
50-289/74-18 Docket No: 50-70o CPPR-40 License No: DPR-50 Licensee:, Metropolitan Edison comoanv Three Mile Island Unit 1 Priority:
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B.1 Category: _
Location:
Middletown, Pennsv1vania
Type of Licensee:
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Y Type of Inspection:
Routine, Announced March 26-29 and April 2-4, 8-12, and 16-19, 1974
, Dates of Inspection:
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'uates of Previous Inspection:
March 20-21, 1974
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N N uMi$s-N 2.-t.
i'/ d 7 v Reporting Inspectotu R. L. Spessard, Reactor Inspector Date f/e/7v 7'/4],
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Acccapanying Inspectors:
J. Streeter, heactor. Inspector (April 12, 1974 onIy>
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R. J UMeyer, Rac.iation Specialis t (April 17, 1974 Date culy)
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R. H. Brickley, kcactor inspector (April 16-17, 1974 Date only)
Date
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None Other Accompanying Personnel:
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Reviewed By:
f Date A. B. Davis, Senior Reactor Inspector, Reactor Operations Branch 1445 031 4910180 [
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SU!CIARY OF FINDINGS
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Enforcenent Action
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A.
Violations None identified
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B.
Safety Items None identified Licensee Action on Previous 1v Identified Enforcement Items A.
The licensee submitted a letter dated' April 11, 1974 in response to
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the violations identified in the RO:I letter dated March 29, 1974 and RO Inspection Reports No. 50-289/74-07 and No. 50-320/74-02. The licensee clarified his response during a telephone conversation on i
April 16, 1974, and these understandings were identified in the RO:I letter dated April 23, 1974. The licensee's corrective action rela-
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tive to Violation 1.b identified in the referenced correspondence s>
was reviewed during this inspection. This item is closed.
(Paragraph 13.a(1)(b))
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The corrective action to the remaining violations was not reviewed and thus remain open.
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The licensee had not submitted a letter in response to the violation B.
identified in the RO:I letter dated April 16, 1974 and RO Inspection Report No. 50-289/74-12 as of the completion of this inspection.
This item remains open.
Design Chances A.
This design change was reported pursuant to 10 CFR.50.55(e) in Met Ed's letter dated April 5,1974 to the This Deputy Director for Reactor Projects, Directorate of Licensing.
change will be reviewed during a subsecuent R0 inspection.
B.
Makeup and Purification System Orifices.
As a result of problens orifices of experienced with similar orifices at another f acility, a new design are to be installed at TM1-1.
This design change will be reported pursuant to 10 CFR 50.55(e), and the chang.c will be reviewed durint, a subsecuent RO inspection.
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Unusual occurrences
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A.
Sodium Thiosulf ate Tank Failure.
This occurrence was reported to 10 CFR 50.55(e) in !!ct Ed's letter dated April 11, pursuant 1974 to the Director, Directorate of Regulatorv Operations. The corrective action described in this letter will be revicued during subsequent RO inspections.
B.
Inadvertent transfer of about 20,000 gallons of water from the Reactor Coolant System to the Borated Water Storage Tank, and possible cavitation of Decay Heat Removal Pump 1B and Reactor Building Spray ? ump 1B.
(Paragraph 11)
Other Significant Findines A.
Current
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1.
This RO inspection, which covered a 4 week period, was conducted for the purpose of verifying that the licensee had completed the remaining recuirements necessary for issuance of an operating
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license.
These requirements were completed on April 19, 1974, (i and Facility Operating License No. DPR-50 was issued cn this same date.
(Paragraphs 2-13)
B.
Status of Previous 1v Reported Unresolved Items 1.
The following items are resolvsd:
The remaining facility procedures have been approved.
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n.
(Paragraphs 13. /1)-(5))
b.
The control rod surveillance procedure has been rev? sed.
(Paragraphs 13.a(2)(c) and (3)(a))
Facility procedure approval sequence has been clarified.
c.
(Paragraph 13.a(3)(b))
d.
RO:I review of seven Preventive Maintenance Procedures has been conducted with no outstanding deficiencies.
(Para-graph 13.a(5))
PORC minutes have been clarified for meetings conducted c.
prior to March 21, 1974, and the PORC membership has been revised in the Technical Specifications.
(Paragraph 13.b)
f.
Measures have been taken to correct data recording deficiencies.
(Paragranh 13.d)
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Independent review of facility procedures has been completed.
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(Paragraph 13.a(6))
Lenkage from the Reactor Building to the emergency cooling h.
coils of the RB Air Recirculation Units A and C during the performance of TP 150/3 was determined to be acceptable.
(Paragraph 3.a(9)(b))
Type B (Pentrations) local leak rate testing has been 1.
satisfactorily completed.
(Paragraph 3.a(11))
2.
The following items remain unresolved:
Excessive leakage on the flanged closures of the fuel a.
transfer tubes.
(Paragraph 3.a(9)(a))
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Cocpletion of Type C (Isolation valves) local leak rate b.
testing.
(Paragraph 3.a(10))
C.
New Unresolved Items 1.
1.
Diesel circuitry design changes.
(Paragraph 13.m)
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2.
Documentation for HEPA and Carbon Filters.
(Paragraph 10)
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Managemcnt Interview interviews were conducted on March 29 and April 4 and 12, 1974 Exit during the inspection and on April 19, 1974 at the conclusion of the inspection.
Personnel Attending J. Herbein, Station Superintendent, Met Ed W. Potta, QC Supervisor, Met Ed G. Miller, Test Superintendent, GPUSC J. Barton, Startup and Test Manager, GPUSC S. Levin, Un,it 1 Project Engineer, GPUSC R. Heuard, Project Manager, GPUSC M. Stromberg, Site QA Auditor G. Roshy, QA Specialist T. Sturgeon, QA Specialist The following summarizes the items discussed.
Preoperational testing status and the licensee's commitments to A.
RO:1.
(Paragraph 2)
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Review of preoperational test results and the licen.eee's conmitments B.
t'o RO:I.
(Paragraph 3)
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C.
Overload Protection for E. S. Motor Operated Valves.
(Paragraph 4)
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D.
Prereauisite List for Fuel Loading.
(Paragraph 5)
Initial startup test program and the licensee's commitments to RO:I.
E.
(Paragraph 6)
F.
Administrative controls.
(Paragraph 7)
G.
QA Program for Operations.
(Paragraph 8)
H.
TWG activities.
(Paragraph 9)
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Documentation for HEPA and Carbon Filters and the licensee's I.
commitments to RO:I.
(Paragraph 10)
Inadvertent transfer of water from the Reactor Coolant System and J.
possibic pump cavitation.
(Paragraph 11)
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Reactor Building Sump and feeder drains and the licensee's wi K.
commitments to RO:I.
(Paragraph 12)
Open items from previous RO:I inspections and the licensee's L.
commitments to RO:I.
(Paragraph 13)
Design Changes and the Unusual Occurrence reported /to be raported M.
pursuant to 10 CFR 50.55(e).
(Summary of Findings)
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DETAILS
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1.
Persons Contacted
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Metropolitan Edison Connanv (Me t Ed)
J. Herbein, Station Superintendent J. Floyd, Supervisor of Operations J. Colitz, Station Engineer D. Shovlin, Supervisor of Maintenance J. O'Hanlon, Nuclear Engineer C. Hartman, Plant Engineer R. Summers, Plant Engineer E. Bulmer, Plant Engineer R. Miller, Plant Engineer
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W. Potts, QC Supervisor R. Harper, Control and Instrumentation Foreman B. Rittle, Electrical Maintenance Foreman
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M. Ross, Shift Supervisor G. Wallace, Shift Supervisor J. Chwastyk, Shif t Supervisor
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General Public Utilities Service Cornoration (GPUSC)
W. Hirs t, Manager of Proj ects
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R. Heward, Proj ect Manager S. Levin, Unit 1 Project Engineer R. Burns, Assistant Proj ect Manager, Engineering g
J. Barton, Startup and Test Manager
G. Miller, Test Superintendent R. Toole, Assis tant Tes t Superintendent
M. Nelson, Technical Engineer j
J. Wright, Site QA lbnager
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M. Stromberg, Site QA Auditor
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T. Sturgeon, QA Spraialist W. Behrle, HFT and Pet Program Coordinator g
T. Faulkner, Senior Test Planner i
R. Claussen,' Lead I&C Engineer i
R. Rathsam, I&E Engineer
Gilbert Associates, Incorncrated (CAI)
W. Sommers, Lead Startup Engineer
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P. Shipper, Prcject Electrical Engineer P. Moyer, Startup and Te.t Engineer
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Babcock and Wilcox, Incorporated (B&W)
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J. Phinney, Startup Manager 2.
Preoperational TestinV" Status
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Tests Completed and Accepted 68%
Tests Partially Completed and Accepted 21%
1%
Tests Completed and Under Review 10%
Tests Not Completed The liccasee evaluated the overall results of the preoperational test program and concluded that the program was sufficiently complete to support (relative to safety) initial fuel loading.
A licensee repre-sentative stated that the tests listed below would be completed and accepted by the TWG prior to initidl criticality with the exceptions
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i as noted.
I TP 153/3 Fluid Block System Functional Verification.
l a.
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b.
SP 102.6 Fire Protection System Checkout.
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TP 120/3 Fuel Handling System Integrated Functional Test.
c.
Test is to be performed using a dummy assembly prior to initial fuel load.
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d.
TP 302/2B In-Core Detector Pre-Installation Electrical Test.
Test is to be performed prior to installation of the reactor vessel head.
F1104/14E Reactor Building Industrial Cooler System Functional e.
Verification.
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Test will probably be completed prior to initial criticality; howaver, the commitment was to complete this test prior to power operations.
f.
TP 160/3 Reactor BuiliL.g Purge System Functional Test.
g.
TP 200/1 Reactor Internals Vent Valve Inspection Test.
I Test will be pcrformed prior to installation of the reactor vessel head.
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TP 305/2 Reactor Protection System Response Time Test.
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~" 600/25 Hydrogen Addition Test.
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TP 6f./26 Degasification Test.
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SP 166.2 Plant Test Panel Pre dp. Alignment.
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3.
Preoperational Test Results
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a.
Detailed Review by RO:I The inspectors conducted a detailed review of the completed preoperational test procedures (Of ficial Field Copy) listed below.
These procedures had been accepted and/or partially accepted by the licensee.
No apparent deficiencies relative to Test Instructions No. 9 and 18, were identified.
Test results
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were satisfactory, and all test reauirements were satisfactorily performed or were properly identified for retest during the post fuel load precritical testing program.
Unless otherwise indi-cated the inspectors had no further cuestions on these test results, and licensee commitments to RO:I are included, as
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appropriate.
(1) TP 202/7, Makeup and Purification System E. S. Test.
' Also included in the inspector's review of this completed test package was the licensee's resolution of previously identified test deficiencies, and the retest results of Makeup Punp MU-PlB.
This item is closed.
(R0 Inspection Report 50-289/74-02, Paragraphs 2.f(2) and 10)
(2) TP 256/4 Loss of Instrument Air Test.
(3) TP 202/3 Makeup and Purification System Functional Test.
(4) TP 600/15 Non-Nuclear Instrumentation Hot Operation Calibratica.
(5) TP 600/20 Loss of Electrical Pouer Test (Without E. S.).
(6) TP 153/4 Fluid Block System Actuation Time Determination.
According t'o the FFAR (Section 5.3.5.2), the fluid block tanks are normally maintained continuously pressuri=ed to 100 psig.
llowever, the licensee has determined these tanks can only be pressurized to 84 psig.
This matter was reviewed by GAI and was determined to be acceptable.
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Additionally, the test and acceprance criteria were based
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on actuation of the system with the tanks pressurized to
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84 psig.
A licensee representative stated that the FSAR would be revised to reflect the as built design.
Item remains open_pending submittal of the FSAR amendment.
(7) TP 160/4 Reactor Building Fans Functional Verification.
After satisfactory performance of this test and acceptance by the TWG, 1 of the 3 fan motors malfunctioned and was returned to the vendor for repairs.
Following repairs and installation of this fan motor, a retest of the fan will be performed.
Licensee believes this can be completed prior to initial criticality; Tech Specs require a minimum of 2 fans.
Item remains open and will be reviewed during a subsequent RO inspection.
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(8) TP 251/1 Reactor Building Sump, Auxiliary Building Sump and
Compartment Leak Detectors Functional Test.
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(9)
TP 150/3 Initici Reactor Building Integrated Leak Rate Test.
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(a)
Fuel Transfer Tubes The licensee accepted the test results with one
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outstanding deficiency involving excessive leakage
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on the flanged closures of the fuel transfer tubes.
Item remains unresolved pending completion of cor-
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rective action which is to occur prior to initial criticality, per a licensee representative's commit-ment to RO:1.
(R0 Inspection Report No. 50-289/74-12, Paragraph 2.d(3))
(b)
Emernency Cooline Coils of RB Air Recirculation Units The licensee accepted the test results with identified leakage from the Reactor Building to the emergency cooling coils of RB Air Recirculation Units A and C en the basis that these coils would be pressurized
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during a LOCA to greater than the calculated peak Reactor Building internal pressure (55 psig).
The inspector verified by review cf test results (TP 160/2 Reactor Building Emergency Cooling Water System) the ability of this system to maintain the cooling coil pressure at 60 psig with one pump and greater than 96 psig with two pumps.
Item is resolved.
(R0 Inspection P.eport 50-289/74-12, Paragraph 2.d(5))
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(c)
Adiustment to ILRf Results
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The Reactor Building Industrial e oler System was lined The up during the ILRT to provide building cooling.
inspector stated that-this system is assumed by the
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Directorate of Licensing to rupture as a result of a LOCA and that during a LOCA the system Reactor Builliag isolation valves vould be closed and be directly sub-The inspe:-
jected to the internal building nressure.
tor stated that since these isolation valves (RE-V 2
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and RB-V7) were not exposed to pressure conditions during a LOCA, the Type C test results for these valves would be required to be added to the Type A results accepted by the licensea. The licensee stated that this would be done.
The inspector has no further ques-tions on this matter at'this time.
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()0) TP 151/1 Recctor Euilding Isolation Valve Leak Tests.
Test results were partially accepted by the licensee with i
3 valves (RD-V2, RB-V7, and DM-V22A) remaining to be tested.
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tested and the results accepted by the TUG prior to initial criticality.
This item remains unresolved.
(R0 Inspection
- Report No. 50-289/74-12, Paragraph 6)
(11) TP 154/3 Penetration Pressurization System Operational Test.
Type B (Penetration) local leak rate testing was conducted
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as part of this test, and the results were 6.2 SCFH as ccm-pared to the acceptance criterion of 8.33 SCFH (0.1 La).
This item is resolved.
(R0 Inspection Report No. 50-289/
74-12, Paragraph 6)
(12) TP 266/4 Nuclear Service River Water Functional Test.
Test resulte. were partially accepted by the licensee for 2 of the 3 pumps.
Following repairs, installation, and test-Licensee ing of the third pump, this test will be completed.
believes test can be completed prior to initial criticality; Tech Specs recuire minimum of 2 pumps.
Item remains open and will be reviewed during a subscouent RO inspection.
(13) TP 310/4 E. S. Annunciator and Alarm Test.
Test results were partially accepted by the licensee with open test requirements an certain breakers which f eed the
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Nuclear Service River 2 ter pumps.
A licensee representa-r t1s tive stated these items would be completed a d th
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Item accepted by the TWG prior to initial criticality.
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remains open and will be reviewed during a subscauent RO inspection.
(14) TP 600/21 Integrated E. S. Test.
Test results were partially accepted by the licensee with Action to two open tect exceptions and one deficiency.
resolve these items was in progress.
Additionally, these items did not affect the objective or the overall results of this test.
A licensee representative stated that the test results would be fully accepted by the TWG prior to initial criticality.
Item remains open and will L reviewed during a subsequent RO inspection.
This test included a requirebent to verify that the
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Reactor Building Spray Pumos reach rated speed in < 6 seconds during block loading on the Diesel Generator.
Test data indicated this requirement was satisfied, i.e.,
BS-PlA reached running speed in 2.40 seconds and BS-PIB reached running speed in 2.48 seconds (as determined from the brush recorder trace of motor current as a function of
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time following Block 4 loading).
The licensee committed to this test requirement in a letter dated Februcry 4, 1974
. to the Director, Directorate of Regulatory Operations.
b.
Verification Review by RO:I The inspectors verified by review of completed test procedures (Official Field Copy) that the procedures listed below had been Also accepted and/or partially accepted by the licensee.
included in this review (on a samnling basis) was the licensee's disposition of identified test exceptions and deficiencies and Unless other-comparison of test data with acceptance criteria.
wise indicated the inspectors had no #urther cuestions on these test results, and licensee. ccmmitmer to RO:I are included, as appropriate.
(1) Test Results Accented (a)
SP 53.10 Reactor Vessel Head Service Structure Temperature Profile Determination.
(b)
TP 600/17 Control Rod Drive Operational Test.
(c) TP 600/24 Unit Cooldown Test.
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(d) F1104/40 Plant Sunn and Drainage System Functional verification.
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F1104/29D LWDS Functiona) 7erification - Decay Heat (e)
Water Cleanup Processes.
F1104/29I LWDS Functional Verit ication - Transfers (f)
from R. C. Drain Tank.
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F1104/29J LWDS Functional Verification - Transfers (g)
through Reactor Drair. Pump.
F1104/29A LWDS Functional Verification - Reactor (h)
Coolant Cleanup Processes.
TF 800/36 (HFT) Shutdown from Outside the Control Room (i)
as Modified for Hot Functional Testing.
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SP 320/2 Integrated C'ontrol System - Open Loop
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Calibration.
TP 350/1 Computer System - Field Verification (Hardware).
(k)
(1)
TP 172/2C Control Building Ventilation System Functional Verification.
TP 180/3 Fire Protection System Functional Verification.
(m)
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TP 302/2A In-Core Detector Cabling Checks and Computer (n)
Input Verifications.
SP 320/3 Integrated Control System Interface Test.
(o)
TP 600/14 Pipe and Component Hanger Hot Deflection and (p)
Inspection.
(q)
TP 600/3 Soluble Poison Concentration Control.
(r) TP 150/2 Reactor Building Proof Test.
.(s)
TP 150/4 Post Accident Purge System Functional Test.
According to the FSAR ' Supplement 1, Part II, Section 6),
this system has 3 para.~lel flow paths with the follouing performance characteri. tics:
high flow (100-1000 SCFM),
medium flow (20-200 SCFM), and low flow (4-40 SCFM).
However, the licensee determined the maxinum flow rate for each path to be high flow = 750 SCEM, medium flow =
173 SCFM, and low flow = 13 SCFM and a maximum ficw
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rate for the combined paths to be 797.5 SCFM vice the 1425.142
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acceptance criterion of > 1000 SCFM. This matter was
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reviewed by GAI and was determined to be acceptable.
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A licensee representative stated that the FSAR wculd be revised to reflect the as built design.
Item remains open pending submittal of the FSAR amendment.
(2) Test Results Partially Accepted These results were partially ac:epted by the licensee to include all safaty related functions required to support initial fuel loading.
A licensee representative stated that the outstanding test requirements would be completed and the results accepted by the TWG prior to initial criticality.
(a)
F1104/15A Auxiliary Building and Fuel Handling Building
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Ventilation Functional Verificatien.
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(b) TP 271/4 Main and Auxiliary Steam Functi..:a1 Test.
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(c)
TP 600/5 Nuclear Chemical Addition and Sampling System i<'
Operational Test.
(d) TP 310/3 E. S. Detection and Actuation Test.
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(e)
TP 120/1 Fuel Handling Systen Operational and Functional Test.
(f)
TP 120/2 Dry Fuel Handling Test.
(g)
F1104/29E LWDS Functional Verification - Bleed and Feed Processes.
(h)
TP 301/2 N. I. Detector Cabling and Response Tests.
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TP 301/3D N. I. - Determination and Setting of Detector
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Voltage.
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TP 600/28 Controlling Procedure for Hot Functional Testing.
(k)
TP 600/29 Reactor Coolant System Thermal Expansion Functional Test.
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(1) TP 609/4 Makeup and Purification Systcm Operational Test.
(m) TP 600/11 Er.orgency Feed System and OTSG Level Contral Test.
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- The inspector met with cognizant licensee representatives and discussed his review of the following procedures which were initial and/or final approved by the TUG:
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(2) TP 200/12D Reactor Coolant Flow Coastdown Test.
(3) SP 710/2 Controlling Procedure for Post Core Load Precritical Testing.
(4) TP 710/1 Zero Power Test.
(5) TP 800/5 Reactivity Coefficients at Power.
(6) TP 800/11 Core Power Distribution.
(7) TP 800/14 Turbine / Reactor Trip Test.
(8) TP 800/18 Power Imbalance Detector Correlation Test.
(9) TP 800/32 Loss of Of fsite Power Test.
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(10) TP 800/34 Cenerator Trip Test.
The inspector had no questions on TP 200/12D and TP 800/18 (Items (2) and (8) above).
With respect to the other proce-dures, the inspector identified certain areas of concern which
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required resolution, and the licensee representatives agreed
. (_j Prior to the to revise the procedures to resolve these items.
completion of this RO inspection, the inspector reviewed TCi-1 to TP 330/5 (Item (1) above) which resolved the items identified Additionally, TP 330/5 met the minimum RO by the inspector.
(R0 Inspection requirements relative to drop t'ime measurements. Items (3) through (7),
50-289/73-22, Paragraph 3.g)
Report No.
(9), and (10) above remain open and will be reviewed during subsequent RO inspections.
7.
Administrative Controls
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The inspector reviewed the implementation of Standing orders 13 and This review was made 14 and Administrative Procedure A. P. 1016.
on a sampling basis and included the following:
Do-Not-Operate Log and Do-Not-Operate Tags.
a.
b.
Out of Service Status Board.
Maintenance Work Recuest Log.
c.
Completed Work Reauests (No. 769 and No. 820).
d.
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No deficiencies were observed by the inspector.
8.
QA Procram For Operations The inspector reviewed the impicmentation of certain requirenentsThe a
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in the licensce's program.
findings were as follows:
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Onsite Staffing (Met Ed)_
a.
The onsite OC staff consisted of 1 QC Supervisor, 4 QC Assistants,
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Additio.nally, 2 QC Assistants had been and 1 QC Specialist.
to the site in May 1974. The hired and were scheduled to report qualificationc of the present staff and the 2 projected additions were reviewed and com/cred with QA Procedure A-II-1, QC Education No deficiencies were identified.
and Training.
b.
OC Trainine (Met Ed)
This subject was reviewed with a cognizant licensee representative, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> / day on who indicated that QC personnel were averaging about training.
The inspector was informed that the program requirements
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contained in QC Procedure A-II-1, QC Education and Training, were under revision to improve training methods and provide better
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documentation of training received. The inspector observed that a training file existed for each individual, and selected one Documentation contained in this file of the files for review.
indicated training consistent with Procedure A-II-l had been The inspector was informed that the licensee's target
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received.
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date for completior; of the revised training program (Informal
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portion) was June 30, 1974. The inspector has no further ques-tions on training at this time.
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Audits (Met Ed)
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c.
The audit program being implemented by the site QC staff was
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reviewed and compared with QA Procedure A-XVIII-1, Audit Program, This review and QA Procedure A-II-1, Reporting Requirements.
was performed on a sampling basis and included the following:
Instruction No. 1 dated October 8, 1973 which (1) QC Supplement is an implementing procedure relative to planning and con-ducting audits and disposition of audit findings.
(2) QC Program Activity Plans (Form QC-5) for the period 1973-March 31, 1974. This form contains September 24, the inspection, surveillance, and audit activities planned for a 13 week period.
(3) QC Program Work Plans (Form QC-3) for the period Septcmber 24, 1973-March 31, 1974. This form contains the work plan for performing inspection, surveillance, and audits scheduled by Form QC-5.
I The Problem Follosup (4) Method established for followup action.
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and NCR Log is used for this purpose, and performance of followup action is scheduled and assigned by Forms QC-5 and QC-3.
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(5) Documentation relative to Audits No. 74-2 and 74-8.
The activities covered by these audits and the audit criteria
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were as follows:
(a) Shif t Relief - Audited against A. P.1012, QAP C-XLV-3, FSAR, Operating Memos, and Standing Orders.
(b) Technical Specification Surveillance - Audited against
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A. P. 1010, FSAR, and Regulatory Guide 1.22.
(6) Biueekly QC Status Report for the period March 1-15, 1974.
This report is submitted by the QC Supervisor to the Manager i
of Operational Quality Assurance.
The program summarizes
the quality program conducted during the period, includes a summary of open items and UCR status, and identifies train-
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ing received by QC personnel.
No deficiencies relative to implementation of the audit program were identified.
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d.
Audits (GPUSC OA)
+
Documentation relative to Audits 74-09 and 74-20 were reviewed and compared with Appendix A of the QA Plan For Startup and Test.
These audits covered activities being practiced by Met Ed.
These activities and the audit criteria were as follows:
(1) Control of Measuring and Test Eauipment - Audited against A. P. 1022 and QAP C-XII-1.
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(2) Tagging Procedures - Audited against A. P.1002.
No deficiencies were identified.
c.
Resolution of Audit Findines The inspector discussed the results of his review of the Met Ed QC and GPUSC QA audit findings against activities being prac-ticed by Met Ed with Met Ed Site Management.
The inspector expressed concern that recent findings by GPUSC QA and open findings from several Met Ed QC audits revealed weaknesses in Management Systems established by Met Ed and asked what stens would be taken to resolve these findings.
The inspector was informed that every ef fort would be made to resolve these items before issuance of an opera:ing license and that during weekly (_,
meetings with department heads, reauirements of administrative procedures and the status of audit findings vould be revieved.
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Throughout the inspection, the inspector monitored the progress made by the licensee to resolve this matter, and the licensce's
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action was completed prior to licensing. The inspector has no further questions on this matter at this time.
9.
TUG Activities The inspector reviewed TUC Meeting minutes for the period February 26-March 19,1974 (Meetings 89-93). Additionally, the inspector audited TWG meetings conducted on April 17,18, and 19,1974 (Moetings 100-102) during which time preoperational test results and the Prereauisite List for Fuel Loading were evaluated and approved.
The inspector observed that TWG activities were in accordance with the recuirements
,
of the Test Manual.
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l 10.
Documentation for HEPA and Carbon Filters
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The inspector reviewed l'urchase Order 99469 which contained the specifications on the HEPA and Carbon filters used in the various
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i The review indicated that filters plant exhaust and cleanup systems.
l ( 'T were supplied in accordance with the required specifications as deternined from a recorded certification by the licensee's OA groun.
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the The certification was based on inspactions by this group at vendor's plant during f abrication of.the filters.
Specific test data an,d certifications defined in the specifications were on file Gas Life Test, Wash Test, Ignition
with the following exceptions:
The licensee was Temperature Test, and Carbon Tetradhloride Test.
The vendor unable to find these records, and contacted the vendor.
certified by TUX dated April 18, 1974 that the tests had been con-ducted and that all test requirements had been met.
Additionally, the vendor stated that formal certification would be provided to the site the week of April 22, 1974. A licensee representative stated that the QA group would audit the certifications provided This action is to be com-by the vender to verify their adequacy.
pleted prior to initial criticality.
(Met Ed letter dated
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April 19, 1974 to the Director, Directorate of Regulatory Opc a-tions, Region I.)
Item is unresolved.
Inadvertent Transfer of Water f rom the Reactor Coolant Systen and 11.
Possible Punn Cavitation The inspector reviewed a CPU Unusual Occurrence Report (No. 14)
dated March 23, 1974 describing this event and discussed the details of this event with cognizant licensee representatives.
This repert was prepared in accordance with the renuirements of Test Instruction No. S.
The following information was obtained:
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1445 049
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the plant was in cold shutdown with the Reactor On March 24, 1074, 90*F, partially drained (100" in the pressurizer)
Coolant Sys tem at No fuel was in the reactor vessel.
and high point vents open.
Pump DH-PlB was operating to recirculate the Reactor Coolant Sys-
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tem to obtain a boron sample. Using an approved operating proce-dure, Pump BS-PlB was started to recirculate the Borated Water About 11 minutes later Storage Tank to obtain a boron sample.
the operator observed that Punp DR-PlB flow was 50% of normal and Pump BS-PlB then noted a 0" level indication in the pressurizer.
was immediately stopped, and Pump DH-PIB was stopped about one As a result, approximately 20,000 gallons of water minute later.
from the Reactor Coolant System were pumped to the Borated Water Storage Tank and Pumps BS-PlB and DH-PlB were operated to near At the time of this occurrence the Low Low Pressurizer cavitation.
Level Alarm (setpoint 80") was out of service for calibration.
The licensee's evaluation disclosed that Nucicar Safety was not
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involved.
Surveillance tests were performed on both pumps to verify flow and normal bearing temperatures.
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Tha inspector observed that the approved procedure used for this
n plant evolution did not provide adequate guidance relative to
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valve lineup.
The licensce's proposed correction ac' tion consisted of the following:
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a.
Revision of procedures.
Review of occurrence with personnel involve 6 and all Operations b.
department personnel.
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Issuance ef an operating Memo stressing the use of proper
!
c.
procedures and adherence to procedures.
Provide more definitive guidance to shift supervisors when d.
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plant evolutions are requested to be performed.
12.
Reactor Buildine Sumn and Feeder Drains I
The inspector made a physical inspection of the facility to determine
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the licensce's apparent readiness to load fuel.
The inspector the Reactor Building Sump and several of the floor observed that A licensee feed this sump were full of dirt and debris.
drains that representative indicated an awareness of this matter, and he stated
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the sump and drains would be cleaned and painted during fuel that 1445 050
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loading and, additionally, the drains would be flushed to the sunp Item and final inspected / cleaned prior to initial criticality.
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remains open and will be reviewed during a subsequent RO inspection.
13.
Onen Itens from Previous RO:I Inspections
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Facility Procedures Program a.
.
Based on a review of facility records and procedures and the discussions with cognizant licensee representatives, inspector determined the following:
(1) Operating Procedures
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(a) The one remaining procedure (1104-50, Sludge Facility and Industrial Easte) has'been final approved.
(R0
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Inspection Report No. 50-289/74-13, Paragraph 10)
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(b) Procedure 1104-36, River Water Chlorination System has
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been revised (P.av. 3, dated April 8,1974) to recuire, i
I (, j as a prerequisite for chlorinator use, that chlorine residuals be monitored during chlorination.
(R0 Inspection Re ort Nos. 50-289/74-07 and 50-320/74-02, Paragraph 7.a)
. (c) Operating procedures have been revised, as appropriate, to incorporate changes created by FS AR Amendment 47, dated Itarch 8, 1974.
These procedures were being typed and will be issued prior to initial criticality.
This iten is resolved.
Issuance of the revised procedures prior to initial criticality (Item (c) above) vill be verified during a subsequent RO inspection.
(2) Surveillance Test and Calibration Procedures (a) Procedures 1301-6.4, 1301-4.7, 1303-2.1 - Weekly, and
. 1303-2.1 - Monthly have been deleted from the Surveil-lance Procedure Index because these test requirements were contained in other surveillance test procedures.
Procedure 1303-11.8 has been approved.
One procedure (1301-9.1, Inservice Tendon Surveillance Program)
remains to be approved, and this is to be done 90 days prior to test performance.
(R0 Inspec.' ion Report No. 50-289/74-13, Paragraph 10)
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(b) Surveillance procedures have been revised, as appropriate,
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new procedures have been written and approved, and the Surveillance Procedure Index has been revised to incor-porate changes created by FSAR knendment 47, dated March 8, 1974.
These procedures were being typed and will be issued prior to initial criticality.
(c) Procedure 1301-92, Control Rod Program Surveillance has been revised to incorporate RO:I comments relative to locking of cabinetc.
(R0 Inspection Report No. 50-289/
74-13, Paragraph 5)
(d) Procedure 1301-9.9 has been approved, and provides for inspection of pipe supports, hangers, and seismic restraints on safety related systems at refueling intervals.
(R0 Inspection Report No. 50-289/73-23,
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Management Interview Item D)
(e) Procedure 1303-8.1 has been approved, and provides for inspection of the Reactor Coolant System to detect
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leakage at an early stage following openinc, repair,
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or modification to this system.
(R0 Inspection Report
No. 50-289/73-06, Paragraph 9)
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.This item is resolved.
The one remaining procedure to be approved (Item (a) above) and issuance of the revised pro-cedures prior to criticality (Item (b) above) will be verified during subsequent RO inspections.
(3) Administrative Procedures (a) Procedure A. P. 1011.2, Controlled Key Locker Control has been revised to incorporate RO:I connents relative to locking of cabinets including the CRD Transfer Cabinets.
(R0 Inspection Report No. 50-289/74-13, Paragraph 5)
(b) Procedure A. P. 1001, TMI Document Control has been revised to include Figure 1001-1 (Procedure Cover
Sheet) which provides for certification of incorpora-tion of concents above (before) the Station Superinten-dent's signature. Additionally, by letter dated March 18, 1974 the Station Superintendent certified his approval of procedures promulgated before the cover sheet change.
(R0 Inspection Report No. 50-289/
74-13, Paragraph 3)
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1445 052 This item is resolved.
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(4) Alarm Procedures
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Alarm procedures have been final approved. This item is resolved.
(RO Inspection Report No. 50-289/74-05, Para-graph 6.f(5))
(5) Preventive Maintenance Procedures The following procedures were reviewed:
(a) Flow Loop Calibration.
(b) Electric Motors; Lubrication of Greased Fearings.
(c) Building Inspections.
(d) Main and Auxiliary Vacuum Pumps - Overhaul.
(e) OSP No. 1 - Mechanical. Inspection.
(f) OSP No. 2 - Rotation of Equipmenc, Valve Cycling and Lubrication.
(g) OSP No. 3 - 480V E. S. Bus Undervoltage Relay Test.
(' 4 No deficiencies were identified, and previous RO:I cccments had been incorporated, as appropriate. This item is
resolved.
(R0' Inspection Reports No. 50-289/73-23, Para-graphs 5.a(6) and (7), 50-289/74-05, Paragraph 7.f(3), and 50-289/74-13, Paragraph 7)
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(6) Independent Review of Facility Procedures The two remaining procedures selected by the General Office Review Board (G0RB) for independent review have been returned with comments. This item is resolved.
(R0 Inspection Report No. 50-289/74-13, Paragraph 13)
b.
PORC Constitution By letter from the PORC Chairman to *he Station Superintendent, PORC minutes for meetings conducted prior to March 21, 1974 were revised to clarify the PORC's review of work requests.
Additionally, the Technical Specifications issued with License No. DPR-50 revised the PORC membership as previously contained in the FSAR, e.g., of f site member participation in PORC proceedings has been deleted. This item is resolved.
(R0 Inspection Report No. 50-2S9/74-13, Paragraph 6)
c.
Met Ed Instrument Shon_
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Equipment for cleaning of gauges has been roccived. This item is closed.
(R0 Inspection Report 50-289/73-22, Paragraph 5)
1445 053
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d Data Recording By letter from the GPU Test Superintendent to satisfactory and unsatisfactory practices for data recording Additionally, the Station Superintendent were identified.
promulgated this information by memo to cognizant Met Ed per-As a long term corrective measure, Test Instruction Nc. 3, Briefing and Dry Run is to be revised to specifyThis item is reso sonnel.
satisfactory data recording practices.
Paragraphs 2.a(3) and
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50-289/74-13, (R0 Inspaction Report No.
(4))
Decay Heat Removal System Valves DH-V38A and B_
e.
Installation of remote manual operators on these valves has been completed. This item is closed.
(R0 Inspection Report No.
Management Interview Item A)
50-289/74-02, Inclusion of Static Head Corrections in Calibration Proce
,
f.
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The review of instrumentation in the Primary System, Secondary and Engineer Safeguardo Systems to identify corr Plant, has been completed.
A Set Ed administrative proce-instruments have been updated.
dure has been written relative to the use of the calibration The Surveillance Test Program incorporates source documents.
the required instrument calibrations, and af fected instruments This item is closed.
(R0 Inspection have been calibrated.
Report No. 50-259/74-02, Management Interview Item A)
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Surveillance Testing Procram g.
schedule records The Surveillance Procedure Index and test were reviewed with cognizant licensee representatices toThe determine the degree of implementation of the program.
had been implemented or was scheduled for im for to fuel loading for those systems and components available In some cases results from preoperational tests are to vice conduct of a surveillance test.
be used as the initial teste.g., Diesel Generator Annual Inspectio ing ILRT, Reactor Duilding Spray System (Compressed Air Tes test, Control Rods (Drop Times), Main Steam Saf ety Valves, Filter Testing (Control Room and Reactor Building Purge Exhaust),
Reactor Building Local Leakage Rate, Inservice Inspection, Manufacturcr's test and Ring Girder Inspection Program.
1415 154
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reports are to be used as the initial test for the pressurizer safety valves setpoint test.
Several tests remain to be con-
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ducted and/or completed prior to initial criticality, and these have been identified by the licensee; many of these tests were verified during the hot functional test program.
This item is closed.
(R0 Inspection Report 50-289/74-02, Paragraph 5)
h.
Control Rod Droo Time Measurements The inspector's review of TP 330/5 CRD Trip Test disclosed that drop time measurements will be made in accordance with the licensee's commitments to RO:1. This item is closed.
(R0 Inspection Report No. 50-289/73-22, Paragraph 3.g)
.
1.
Amendment to the FSAR The licensee submitted revised tables to Section 13 of the FSAR to the Directorate of Licensing. This item is closed.
(R0 Inspection Report No. 50-289/73-22, Paragraph 3.b)
i g-
- w j. Malfunction of Diesel Generators _
The Problem Report, which identified the common design feature that caused Diesel Generator malfunctions at other facilities, has been reviewed and evalua.ted by GAI.
This problem was determined not to be applicable at TMI-1.
This item is closed.
(R0 Inspection Report No. 50-289/74-02, Paragraph 9)
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k.
Alternate Control Station Instrumentation Periodic comparison checks of the temporary instrumentation installed at this station have been implemented by adding this requirement to the Weekly Surveillance Checks contained in the Operations Surveillance Book. This item is closed.
(R0 Inspection Report 50-239/74-08, Patagraph 2.d(2))
1.
Steam Driven Emercency Feedwater Pumn Repairs to this pump have been completed, and the pump was tested using auxiliary steam to verify operability.
Additional testing of this pump is to be donc during the post core load procritical testing program. This item is closed.
The results of additional testing (completion of TP 600/11) will be reviewed during a sub-sequent R0 inspection.
(R0 Inspection Report No. 50-2S9/74-OS, Paragraph 2.d(1))
1445 055
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Diesel Generators Startuo Malfunction g.
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to 10 CFR This event was reported by the licensee pursuant 50.55(e).
(Met Ed Letters dated April 4, 1974 and April 22, 1974* and RO Insp6ttion Report 50-289/74-08, Unusual Occur-rences Item L.)
The inspector verified by review of records, discussions with cognizant licensee representatives, and visual examination that the licensee's action as stated in the referenced letters had been completed.
Additionally, facility drawings have been updated to reflect GAI's decign changes.
The design change to clininate a single failure from deactivating both start circuits of the diesel generator consisted of rewiring the contacts from the low speed switch and lube oil switch in parallel with each other (contacts were previously wired ia series). Other GAI circuitry changes which were made or approved for installation were for opera-
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tional convenience (eliminate possibility of energizing the automatic shutdown relay following shut down of the diesel generator) and for test purposes.
!,'(>
The inspector was provided with updated drawings of the diesel
_
generator circuitry, and the licensee representatives were informed that these drawings would be further reviewed in the RO:I office. The inspector expressed concern about the design change which paralleled the contacts from the low speed switch and lube oil switch because the potential for a single failure exists which could prevent the start relays This from being de-energizo.d during startup of the engine.
condition would cause both air start solenoid valves to remain open, and thus lead to continuous blowdown of the air receiver tanks for the engine.
Additionally, the status of the start relays is not monitored to alert an operator of an abnormal condition, i.e., the original condition leading to the design change was unknown to the opetator, and the condition postulated as a result of the design change would likewise go undetected.
A licensee representative indicated the diesel generator cir-cuitry would be further evaluated based on the inspector's com-ments and that the inspector would be informed of the results a
of this review.
This matter is unresolved pending completion of the licensce's review and evaluation of the results of this revies by RO:I.
n.
Emercency Plannine (1) Meteorolocv Equinment
}jf} }{h
.
The inspector observed that the meteorology instrumentation e
located in the Control Rocm had been connected to the Submitted following completion of this R0 inspection.
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meteorology tower, turned over to Met Ed following testing
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by UESC, and was operable.
This item is closed.
(R0
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Inspection Report No. 50-289/74-10, Paragraph 4)
(2) Communications -
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The inspector verified by review of records and updated facility drawings that the remote transmitter which operates the base radios had been connected to the IC E. S. Valve Motor Control Center which is Diesel supplied
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This item is closed.
(R0 Inspection Report No. 50-289/74-10, Paragraph 5)
(3) Letters of Acreement Letters from 3 physicians who agreed to report to the site
to provide emergency first-aid assistance if needed were reviewed by the inspector.
This item is closed.
(R0 Inspection Report No. 50-289/74-10, Paragraph 6)
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Environnental Monitorine (_)
o.
(1) Chlorine Discharges
, Installation, testing, and operability of the tuo continuous chlorine monitors, one for clant river water discharge (Mechanical Draf t Cooling Tower effluent) and the other for Natural Draf t Cooling Tower blowdown, were reviewed by the inspector.
The monitoring system for plant river water discharge had been installed and testing of the sys-tem by UE&C was in progress.
Turnover of this system to Met Ed was expected to occur the week of April 21, 1974.
The other monitoring system was partially installed, and missing components included a transmitter and recorder.
Due to procurenent delays involving the missing components the licensee did not expect to have this system in opera-tion until July 1974. The licensee has implemented a sampling program, in accordance with the Environmental Technical Specification requirements, until these monitors are operational. This item will be reviewed during sub-sequent RO inspections.
(R0 Inspection Report No. 50-289/
74-07, Paragraph 7.a and Licensee Letters dated April 11, 1974 and April 19, 1074 to the Director, Directorate of Regulatory Operations, Eegion I)
1445 057
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t (2) Thermal Discharecs
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Installation, testing, and operability of the equipment If required by the Environ =cntal Technical Specifications for monitoring the~rmal discharges (located in the Control Room and the Mechanical Draf t Cooling Tower Pumphouse) were Installation of this equipment reviewed by the inspector.
had been completed and testing by UESC was in progress.
to Met Ed was expected to occur Turnover of this equipment The licensee committed to R0:I the week of April 21, 1974.
fuel load to have this equipment operational prior to post This item will be reviewed during a subsequent RO heatup.
inspection.
(R0 Inspection Report No. 50-289/74-07, Para-19, 1974 to the graph 9 and Licensee letter dated April
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Director, Directorate of Regulatory Operations, Region I)
.
Instrument Air Systems Testing p.
The inspector reviewed TP 256/4, Loss of Instrument Air Test No deficiencies were identified and the results of this tect.
(')
relative to performance of test requirements or relative to However, the test results meeting stated acceptance criteria.
this procedure did not include a maximum inspector noted thatflow test on the instrument air system as previously transient A licensee representative indicated that committed to RO:I.
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the performance of such a tes.t had been reviewed by GAI and that it had been concluded that such a test was not necessary from the standpoint of improving the test program or for verifying adequacy of design for the following reasons:
(1) The system was designed with suf ficient capacity for handling such plant transients as startups, shutdowns, and loss of instrument air at power, (2) The system design including capacity was verified during (TP 256/3) and during the loss of air its functional test test (TP 256/4). Additionally, the adequacy of design was functional testing where two unit demonstrated during hot heatups and cooldowns were performed with no operational problems being identified relative to insufficient air capacity.
The licensee representative indicated that GPU believed that the intent of the subject test had been met by virtue of their This item is closed.
(R0 Inspection Report
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test program.
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No. 50-289/72-17, Paragraph 3.c)
1445 058
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