IR 05000320/1977010
| ML19220B640 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 04/11/1977 |
| From: | Davis A, Fasano A, Rebelowski T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220B636 | List: |
| References | |
| 50-320-77-10, NUDOCS 7904270157 | |
| Download: ML19220B640 (19) | |
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Reg I Form 12 (Rev Feb 77)
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
IE Inspection Report No:
50-320/77-10 Docket No:
50-320
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Licensee:
Metrocolitan Edison Comoany License No:
CPPR-66 Readino Pennsvivania 19603 Priority:
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Category:
B -l
_ Safeguards Location:
Middletown Pennsylvar.la (TMI-2)
Type of Licensee:
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Type of Inspection:
Routine, Unannounced Dates of Inspection:
M=rch 14-18.1977 Dates of Previous Inspection:
February 23-25, 1977 ffsf 7/
R porting Inspector:
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A. N. Fahano, Reactor nspector DATE
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// [77 Accompanying Inspectors:
DATE T. A. Rebelowsk(, Reactor Inspector DATE
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DATE DATE Other Accompanying Personnel: A. B. Davi;, Section Chief, Reactor
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Projects Section No.1 DATE O
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f////77 Reviewed By:,
Ct_ e A. B. Davis, Chief, Reactor Projects Section No.1 OATE (
Reactor Operations and Nuclear Support Branch
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7904270151
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SUMMARY OF FINDINGS Enforcement Action
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None.
Licensee Action on Previously Identified Enforcement Action Not Inspected.
Design Chanaes Not Inspected.
i Unusual Occurrences None.
Other Significant Findinos A.
Current Findings i
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 under Unresolved Items.)
Preoperational Test Procedure Review, Detail 3.
a.
b.
Test Program Implementation - Document Control, Detail 4.
Previously Identified Unresolved Items, Detail 5.
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Unit 1 Problem Review for Applicability to Unit 2, Detail 8.
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IE Bulletins and Circulars, Detail 9.
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Witness of Flush of Parts of the Makeup System, Detail 10 L
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2.
Unresolved Items
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Item No.
Short Title 77-10-01 Documentation on D/G room fusible links, Detail 3.c.
77-10-02 Functional and sensitivity testing of
chlarine detectors, Detail 6.
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77-10-03 Program development for post D/G mainten-ance testing, Detail 7.
77-10-04 Replacement of BFD relays, Detail 9.c(2).
3.
Inspector Identified Follow-up Items
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77-10-05 Class B cleaning of Makeup System, Detail 10.c( 5).
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B.
Status of Previously Identified /Other Items The following items have been resolved / closed:
Reference Detail 5.
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76-03-04 I (
76-07-03 76-07-05 76-17-02 Management Interviews A.
Entrance Interview Prior to a formal Entrance Interview, the inspector went to Unit 1 and was contacted by the licensee and questioned about unresolved itea 77-03-08. Reference was made to ANSI N18.7-1972, paragraph 4.1, as the basis for the item.
The inspector contacted Unit 1 personnel for the purpose of obtaining a sample of "Furmanite" for NRC independent analysis,
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Inspection Report No. 50-289/77-05.
The licensee assured the inspector that a sample would be made available.
Results frem a sample sent to B&W were not available.
The inspector made a construction site tour prior to contacting Unit 2 mansg ement.
During this tour, the inspector met the Unit 2 Test Super-intendent in front of the Reactor Building equipment hatch of Unit 2 on March 14,1977. The chance meeting resulted into an entrance meeting.
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During this meeting the inspector described the scope, estimated duration, personnel to be contacted and records to be reviewed as part of the inspection. The Test Superintendent informed the in-spector that a flush was planned for the Makeup System on March 15, 1977.
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The inspector conducted a formal entrance interview with the TMI-2 Unit Superintendent and his staff.
Bulletins, Circulars and Reportable Occurrences were discussed.
The inspector stated that the inspection would involve a review to ascertain if experience gained at Unit 1 is being applied to Unit 2.
B.
Exit Interview An exit interview was conducted at the site on March 18,1977, at the conclusion of the inspection with the following licensee attendees:
Metropolitan Edison Company (Met Ed)
Mr. G. P. Miller, TMI-2 Unit Superintendent Mr. J. L. Seelinger, TMI-2 Superintendent - Technical Support Mr. M. Bezilla, p0RC Administrator (
Generai public Utilities (GpU)
Mr. M. Nelson, Technical Engineer Mr. R. Toole. Test Superintendent United Engineers and Constructors, (UE&C)
Mr. S. Kakarla, QC Supervisor, UE&C Startup Detail 2 through Detail ' 0 contain the items d,iscussed at the exit interview.
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DETAILS 1.
Persons Contacted General Public Utilities Service Corporation (GPU)
Mr. A. Duminguez, Test Engineer Mr. R. Fenti QA Auditor Mr. J. W. Garrison, Shift Test Engineer Mr. S. Levin, Project Engineer Mr. M. A. Nelson, Technical Engineer Mr. M. J. Stromberg, Chief Quality Assurance Auditor Mr. R. J. Toole, Test Superintendent fr. J. Ulrich, Shift Test Engineer United Enoineers and Constructors, Incorporated (UE&C)_
Mr. Z. James, QC Engineer Mr. R. Jernigan, Test Engineer Mr. B. Kaufner, Test Engineer 4: Engineer Mr. D. Rhyne,-Group Leader Mechan Metropolitan Edison Company (Met Ed)
I Mr. R. Barley, Lead Mechanical Engineer Mr. M. Bezilla, PORC Administrator. THI-2 Mr. J. J. Colitz, TMI-l Unit Superintendent Mr. R. Evans, H.P. Chemist, Junior Mr. D. Good, Computer Programer Mr. G. P. Miller, TMI-2 Unit Superintendent Mr. J. P. O'Hanlon, Unit 1 Superintendent - Technical Support Mr. J. L. Seelinger, Unit 2 Superintendent - Technical Support Mr. M. A. Shatto, Engineer Associate II, Nuclear 2.
Purpose of the Inspection'
The inspector informed the lic insee that the purpose of the inspection was to:
Review selected Preoperational Test Procedures;
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a.
Review the implementation of the licensee's document control b.
by test personnel during preoperational testing; Review the status of previously identified unresolved items; c.
d.
Review the Chlorine Facility and Chlorine Detection Systems; b
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Review Diasel Maintenance; f.
Review Circulars and Bulletins; g.
Review of Unit 1 Problem Applicability to Unit 2; and, 5.
Witness the conduct of tests in progress (Flushes)
3.
Precoeration ~
t Procedure Review The Office of inspection and Enforcement (IE) Preoperational Inspection Program dealing with Test Procedure Review has the objective of re-viewing safety related Category A tests for consistency with regulatory requirements, guidance and license commitments.
Uniform criteria are applied in the test procedure review to assure
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the technical and administrative adequacy of the procedures.
This program is a sampling program which is an ongoing effort conducted prior to the performance of said tests and, therefore, prior to the issuance of an operating license.
The following procedures were reviewed:
TP 330/1, MTX 38.2, Control Rod Drive Pre-Op Calibration
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TP 330/2, MTX 38.3, Contrcl Rod Drive Control System Operational
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Test TP 180/3, MTX 75.6, Fire Protection System Functional Test
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TP 330/1, MTX 38.2, Control Rod Drive Pre-Op Calibration a.
This procedure addresses the initial application of power to the CRD control system components and the calibration of the components
'to verify acceptable limits.
One area of concern was identified in that the procedure did not provide for documenting the status of l
temporary jumpers that were to remain in the system as a prere-quisite to procedure TP 330/2.
Prior to the conclusion of the inspection, the licensee had written an approved exception that add-essed the status of. temporary test equip:;ent and "as left" systen status.
The inspector has no further questions on this procedure at this time, k._
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b.
_TP 330/2, MTX 38.3, CR0 Control System Operational Test This procedure addresses the following:
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The operation of control panel position indicators;
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The application of power to the aJxiliary and control
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group 5 through 8 regulating power supply cabinet! ;
The ir.terfacing of the plant computer with the pl nt
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annunciator system.
The licensee corrected the procedure documentation with exception to paragraph 9.5 of the procedure. respect action was satisfactory.
The corrective The inspector had no further questions on this procedure at this ti.ne.
180/3, MTX 75.6, Fire protection System c.
This test addresses the testing of the fire pumps, the halogenated explasion suppression system and the deluge
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system located in the air tunnel.
The inspector requested that the licensee address the sprinkler system.
The UE&C diagrams of the hydrostatic system were examined by the inspector. The inspector verified that the sprinkler systems are being hydrostatically tested.
This effort has not been completed. Documentation of the hydrostatic tests was not finalized as of the date of this inspection, but should be upon completion of
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tests.
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The licensee's documentation with respect to the fusible links on the fire screens, that separate the diesel room from the fuel storage area, remains to be inspected This is an unresolved item, 77-10 01,
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of the documentation by the inspector.pending the review
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The above procedures reviewed met the criteria established in tne FSAR and ANSI N18.7-1972 and R.G.1.65 as to procedure format and content.
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4.
Test Procram Implementation - Document Contro_1 The inspector reviewed the licensee's implementation of administrative controls that he has developed in the area of Document Control, a.
Procedure Review and Acoroval
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The inspector selected three recently approved preoperational test procedures to verify that review and approval were in accordance with Test Instruction TI-18.
The three tests selected were:
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TP 310/3, SFAS Actuation and Detection Test TP 330/t., Integrated CRD System Test TP 600/17, Control Rod Drive Operational Test i
The above procedures were sent out for comment on February 9
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(TP 310/3) and February 11 (TP 330/14 and TP 600/17).
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I The inspector reviewed returned comments, the evaluation of these
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comments and the changes incorporated into the approved pro-cedures.
No inadequacies were identified.
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The test procedures reviewed were in conformance with the administrative l g
documents.
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b.
Drawing Selection The inspector relected the following referenced drawings as noted in TP 310/3 and verified that Sheet and Revision were in ac-cordance with the master index.
Drawing Sheet Revision 3073
14 3074
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3074 45A
3075
10 3075 105
l 3075-229B
1 3079 27D
3091
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3091
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3091 168
No variances were identified when compared to the master index.
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The inspector had no further questions on this item at this time.
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c.
Field Chance Drawinos
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The inspector reviewed a recently completed Field Change Request, No. 2355, January 28, 1977.
The change included the modification of damaged MCC 2-11EB.
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T.he Field Change Request indicated the need for redrawing and ap-proval of the following drawings:
Sheet Revision B&R Drawing 3023 3E
3F
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C2R
C3R
C4P
C1 F
C2F5
All drawings were checked against the drawing index and the micro file.
It was found that the stated revisions were maintained (
in house.
The inspector had no further questions on Field Changes at this time.
5.
Previously Identifhd Unresolved Items The following previously identified unresolved items were reviewed.
The items have been resolved:
76-03-04, Precoerational Personnel Training
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The inspector reviewed documentation of tests taken by the personnel involved in the preoperational testing program.
The examination reviewed indicate that the test engineers nave knowledge of the administrative and QA/QC controls to be adhered to during the conduct of the preoperational test program.
This item is resolved.
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76-07-05, BWST Functional Test
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The licensee has addressed low level and high level setpoints that reflect OP-1101-02 Plant Setpoints, dated March 7,1974 The in pector reviewed documentation of GPU problem report
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No discrepancies were noted.
This item is resolved.
76-07-05, Post Core Accident Flood Levels
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A walk through. inspection of the reactor containment in the area of the Reactor Coolant Drain Tanks was made by the inspector.
Checks were made to see that Valve WDL-V6 was removed. The valve has been removed.
The inspector noted that modifications, according to Drawing 2632, were in progress at the time of walk through inspection.
This item is resolved.
76-17-02, Flush Documentation
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The licensee has modified the General Procedure for Cleaning and Flushing System and Components, TP 250/4.
TCN-5, Section 9.2, g
is now included in the test which describes the required method for the updating of flush diagrams and for making revisions to the exit flush paths.
This item is resolved.
6.
Chlorine Detector Testing The inspector's tour. of the site included the Chlorination Building that houses support stands for twenty, one ' ton liquid chlorine con-tainers.
The inspector requested the licensee to discuss the method
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_by which chloriae detectors are calibrated and tested.
The inspector also requested that the operations department review the surveillance documents for these detectors.
There are two (2) chlorine detectors per air intake tunnel that control the closure of damper AH D4092C, Control Room Air Supply, automatically.
The inspector walked the air intake tunnels to ascertain construction status of fire protection systems that were reviewed in detail 3.c of l
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The chlorine detectors were not observed.
The licensee documentation
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indicated that detectors are located at Control Building Air Duct AH CA 5188, AH CA 5484 and in Air Intake Tunnel AH CIS 5188 and 5484 The range of the instruments are indicated to be between 0-6 ppm chlorine detection with a setpoint of 3 ppm.
The licensee stated that a review of the method of calibration and testing of detectors would be conducted.
A test to demonstrate
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the initiation of damper closure within specified criteria would be conducted. This item will be reviewed during a subsequent in-spection for method of testing and control room isolation requirements.
This is unresolved item 77-10-02.
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7.
Diesel Maintenance The inspector discussed the tentative diesel material changes as indicated in the licensee report to IE:I on March 4,1977 as a 10 CFR 50.55(e) design deficiency.
The licensee stated that the following items would be accomplished
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on the diesel generators:
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Inspection of vertical drive for metallurgy identification with a possible replacement of driver.
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Modification of fuel header piping.
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Installation of improved cam roller and inspection of camshaft
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and cam followers.
Discussions with the vendor indicated that the vendor indicated that the vendor design changes include an improved depth hardened cam roller with radius edges.
The inspector reviewed the licensee's purchase specification in the area of shop tests. The inspector stated that additional testing would be required prior to the preoperational test program functional testing of the diesel generators.
These additional tests should in-clude:
An additional four hour full-load test upon completion of material
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changes; A post test examination of material changes upon conclusion of
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testing as required by the or,iginal specification.
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The licensee stated that at the conclusion of diese' maintenance material The changeover, a review of testing requiremer.ts would be conducted.
additional test program will be available for review, witnessing and results review.
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77-10-03, is unresolved pending establishment of the licensee's This item, program for diesel generator testing.at the conclusion of modifications and review by the inspector at a subsequent inspection.
8.
Unit 1 Problem Review for Applicability to Unit 2 Current Acoroach to Problem Apolication a.
Reference Three Mile Island Unit 2 Licensing Concerns Meeting, February 25, 1977.
Item 8 of the referenced meeting minutes addresses the NRC Bul-letins and Circulars with respect to the method to be used to assure that Unit 2 personnel are kept informed.
The minutes stress the need to be aware of Unit 1/ Unit 2 overlap for both unit applicability.
The meeting minutes address the review of Reportable Occurrences A
(RO) and other correspondence for applicability to Unit 2.
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similar method for R0 distribution as 'ar bulletins and circulars has been established.
The establishment of the above should further assure that experience
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gained from Unit 1, and other facilities, is available for con-sideration for applicability to Unit 2 by responsible and involved personnel.
b.
Past Approach to Problem Application Discussions and reviews of documentation indicate that there has
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been a deliberate review of Unit 1 problems for applicability to Unit 2.
The document, MPR Review of TMI il Problems for Ap-plicability to TMI #2, March 12,1975, addresses experience gathered on Unit 1 problems through June,1974.
The mechanisms for handling problems occurring after this study include the close contact of the Unit 1 and Unit 2 Plant Super-intendents, the common use of facility procedures and support
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personnel.
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The inspector took a random sample of occurrences that were reported to NRC and reviewe.' documentation to assure that experience gained from Unit 1 continued to get incorporated into Unit 2 where applicable.
The following occurrences were reviewed:
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(1)
Report dated April 30, 1974, Recirculation Orifices Ex-amined for Erosion.
(2) A0 74-5, A Pinhole Leak Found in the Recirculation Line Orifice of the 1B Makeup Pump.
(3) A0 74-6, Socket Weld, Weld Cracks, on the Water Supply Line from a Makeup Pump.
(4) A0 74-7, Use of Outdated Valve and Checklists from Outdated Procedures.
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Nonroutine Repcrt 74-04, Spherical Nut on the Internals Handling Fixture Not Secured.
(6) A0 75-07, six of Twenty Safeguards Motor Control Units Manufactured by ITE Imperial Corporation were found to have (
Wiring and/or Connector Problems.
(7) A0 75.11. Four High Power Channels were Found to be Incor-rectly Set.
(8)
A0 75-15. The Pressure Transmitter of the Reactor Protecti'.
System Channel B was found Out of Calibration.
(9)
ER /0-8/40, Flow Recorder (FR-123) would not have Closed
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Discharge Valve of the Gas Waste Discharge.
(10) LER 76-12/lT, Reactor Vessel Surveillance Holder Tubes Found Damaged.
With respect to item (1) and (2), this problem had also
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been identified at Arkansas 1.
This problem was one of the probiems addressed for Unit 2 applicability discussed in MPR Review of TMI #1 Problems for Applicability to TMI #2, March 12,1975. Unit 2 will have a proven acceptatle design to preclude a similar problem.
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With respect to item (3), there was no documentation availabie
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that showed direct consideration of this problem to Unit 2.
The MPR Review of TMI #1 Preblem for Applicability to TMI #2, Item B.6 did address caustic attack to stainless steel lines.
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Socket welds were addressed with metallurgist recommendations that socket welds not be used.
Consideration of applicability to Unit 2 were addressed.
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With respect to item (4), Unit 2 Procedure Index Status, printout contains the latest index of the most up-to-date procedures. This is similar to the Unit 1 implemented computerized station pro-cedure index. The Unit 1 and Unit 2 index should assure that the most current procedures are used and so eliminate any use of outdated procedures.
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With respect to item (5), the nonroutine report 74-04 states
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that this item pertains to Unit 2.
This problem was corrected on Unit 2 via a B&W Field Change (FC 41-1) and B&R FCR29, July,1974.
Unit 1 and Unit 2 had similar corrective action.
With respect to item (6), correspondence was reviewed between
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Met Ed to Gpu, dated August 12, 1975 and GPU to Met Ed, dated r
September 9,1975, which addressed this problem for action toward protecting Unit 2 from a similar problem.
Correctiva action was taken in the form of equipment checks.
An im-plementation data sheet, dated December 1,1976, for Unit 2 48V Intarnal Power Wiring shows implementation of precautionary checks.
With respec'. to item (7), which was a procedural error, pro-
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cedures have been corrected for Unit 1.
Surveillance pro-cedures for Unit 2 remain to be written. Unit 1, verified by discussions with Unit 2 personnel, surveillance procedures will be used directly or as guides (as applicable) in dev-eloping Unit 2 surveillance procedures.
Item (7) concerns, as well as other procedural concerns, should be averted for Unit 2.
The Administrative Procedures for Unit 1 are the same for Unit 2.
This via procedure AP 1022, Control of Measuring Test Equipment, Revision 2 April 18,1975, and AP 1023, Test Equipment Recall, Revision 2, March 14,1976, should avert the further concern of using out of calibration and/or non-traceable calibration equipment, k-
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item (8), documentation between B&W and GPU 30, 1976, subject: TMI With respect ts project managers, dated November
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Station, Unit No. 2, RCS Pressure Transmitters, ad provide Unit 2 with a different transmitter that should be the problem.
i ilar more stable under operating conditions and so avert a s m
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problem at Unit 2.
With respect to item (9), this occurrence report contains.
d the recommendation that applict bility to Unit 2 be considere Discussion with licensee person 1el indicate that the design
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is different than Unit 1 design.
l a key operated switch located in the control room vice a to The gener c problem of having the at a remote location. switch, in either Unit, in the byna via administrative controls.
Bypass of Safety Function and Jumper Co With respect to item (10), a new design for the reactor The vessel surveillance holder tubes has been accepted.
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A original design for Unit 2 was different than Unit 1.
The accepted similar problem should not have occurred.
design should avert the problem at Unit 2.
The TMI 2 Unit Superintendent, has agreed to receive Unit 1 Also, he has Reportable Occurrences and other correspondence.
agreed to evaluate or have evaluation made on these item application to Unit 2, Reference Detail, 8.a of this report.
IE Bulletins and Circulars 9.
Selected IE Bulletins and Circulars were reviewed to verify a.
Information was forwarded to onsite management.
Information discussed in the licensee'
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Corrective action taken was effected as describe
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The reply by the licensee was prompt and within the time period in the bulletin letter considering mail delays.
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The IE Bulletins and Circulars reviewed were:
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Circular 76-05, Hydraulic Shock and Sway Suppressors, (1)
October 8,1976.
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(2) Circular 76-02, Relay Failure - Westinghouse BF(ac) and BFD (de) Relays, August 18, 1976.
(3) Circular 76-01/ Bulletin 76-07, Crane Hoist Control - Circuit Modifications, July 28, 1976.
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(4) Bulletin 73-2, Malfunction of Containment Purge Supply Valve Switch, July 18, 1973.
(5)Bulletin 74-12, Incorrect Coils in Westinghouse Type SG Relays at Trojan, October. 23,1974.
The inspector's findings were acceptable except for the Unresolved c.
Items delineated below:
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(1) With respect to Circular 76-05, the licensee's response, November 18,1976, GQM 1591, indicated that ITT Grinnell snubbers are not being used at Unit 2.
Visual inspections made during walk through inspections of Unit 2 revealed that the questionable snubbers are not being used on equipment at Unit 2.
This iten is closed.
(2) With respect to Circular 76-02, QC Checklist No.14271, I
was generated to answer IE Bulletin 76-05, and is applicable to Circular 76-02, Reference Inspection Report 50-320/76-08.
The checklist identifies the location of the relays including those in safety related systems.
The licensee has 40 replacement relays on order for replacing the W BFD relays.
Thirty four
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BFD relays have been identified as being installed in a safety l
related system circuitry. These relays remain to be renlaced.
This is unresolved item 77-10-04 pending receipt of the new relays and final checks for replacement completion.
(3) With respect to Circular 76-01, this circular was reviewed and documented in Unit 1 Inspection Report 50-289/77-03.
The licensee cranes at Unit 1 and 2 are in ccmmon use and/or l
are of the same design. No further action was required by the-i licensee. This item is closed.
I (4) With respect to Bulletin 73-02, Burns and Roe Drawings 2041, i
. Revision 18, and 3079 Sheets 278 and 27C shows line separation with control separation of purge valve exits.
This' item is closed.
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(5) With respect to Bulletin 74-12, correspondence dated November 22,1974, GQL 0501, indicates that the Westinghouse type SG 293-8255A20 Relay is not used at TMI-2.
Checks on similar or equivalent types of relays which might have been improperly labeled were made.
An equivalent Westinghouse type SG 1342925A Relay was found and checked.
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were located in shfety related circuits.
The inspector reviewed the data sheets, dated November 15, 1974.
The coil resistance: were measured and are in the range of 4600 ohms. This iteni is closed.
10. Witness of Flush of Parc of the Makeup System Witnessino - MTX 99.4 Makeuo and Purification System on March 16, 1977 a.
The inspectors witnessed portions of this flush operation from
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midnight to 3:00 a.m. on March 16, 1977.
The inspector's observation of flushing operations of the Makeup System (MU) verified the following:
The flush procedure including the sections of the MU system
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to be flushed was in use.
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The minimum crew requirements were not specified in the flush
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procedure.
A requirement for QC witnessing of the test was met.
Samples were taken from the Demineralized water source
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to assure that Class B water was used in the MU system flush.
" Pillow case" sample collector was available and used to
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check particulate content of effluent water.
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The proper plant systems were in service.
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Jurisdictional control tags were in place at major valves and
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pump locations.
The test crew action was satisfactory.
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b.
Reference Material Reviewed TP 250/4, General Procedure for Cleaning and Flushing Systems
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and Components.
MTX 99.4, Makeup and Purification System Flush, March 12, 1975.
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Unit 1 Chemistry Log.
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Post Flush Review
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(1) Test Fxceptions The following test exceptions were noted in the MTX 99.4
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package:
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Makeup pump internals were removed.
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Groups I, II, III were not completed before doing portions of Group IV flush sequence.
Decay Heat pump used for flush water delivary instead of
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the makeup pumps.
(2)
Flushed pipe Designation _
The pipe notation in the procedure was compared to the drawing,
i B&R 2024, notation. The following was flushed:
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PIA-161-152-154-155 (b)
PI A-161-152-153 g
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PIB-170-164-165 (d)
PI A-151-170-152-153 (e)
PI A-151-120-179-170-152-153 (3) Test Acceptance Criteria
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ph paper readings were noted on the test data sheets and were noted as 5.8.
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The chemistry data results for each path as noted in (2) above from (a) through (e) are as follows:
Path Chloride Conductivity Visual (a)
0.0 0.655 clear (b)
0.03 1.19 clear (c)
0.03 0.636 clear (d)
0.0 0.844 cl ear (e)
0.01 0 "05 cl ear The data indicates acceptable results.
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(4)
Source Water Grade B Conformation The licensee took a sample of the Boron Water Storage Tank (BWST) which is serving as the suction source of grade B water for Unit 2 flushes.
The data, March 16, 1977, indicated that the water was of grade B quality.
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(5)
post Flush Reactor Containment Visual Insoection The inspectors reinspected the pipe terminal locations.
The pipe sections viewed were up stream of MUV152A, B, C and D.
It was noted that the ends of the pipe up stream of t 'st check valves were sealed closed with tape and a plas f t, cover.
Discussions with the licensee indicated that when the ends of these pipes are welded to their respective vessel nozzle connections there will be a visual check and cleaning to assure the maintenance of class B cleanliness.
This is inspector follow-up item 77-10-05 pending final weld connection completion with proof of class B cleanliness.
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