IR 05000352/1979002
| ML19225B052 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 04/05/1979 |
| From: | Durr J, Durr J, Mattia J, Mcgaughy R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19225B025 | List: |
| References | |
| 50-352-79-02, 50-352-79-2, 50-353-79-02, 50-353-79-2, NUDOCS 7907230444 | |
| Download: ML19225B052 (21) | |
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U.S. NUCLEAR REGULA7 RY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
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Region I
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50-352/79-02
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Report No. 50-353/79-02 n. _ g 50-352
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Docket No. 50-353
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CPPR-106
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License No. CPPR-107 Priority
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Category A
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Licensee:
Ph11adelohia Electric Coroanv 2301 Market Street
.a Philadelnhia. Ponnc;yl va n i a 19101 Facility Name: Lim rick cgnorating Tration. Units 1 and 2
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Inspection at: Limerick, Pennsylvania
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Inspection conducted:
February 20-23, 1979
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Inspectors:
~J. Mattia, Reactor Inspector date signed
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7. Durr, Reactor Inspector date signed
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AI Finkel, R3 actor Inspector date signed
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3 fJ.1[ 71 R~. McBrearty, React Inspector date signed
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Approved by:.,h,f [#bu %
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R.McGaughy,C#p,ProjectsSection, v date signed'
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RC&ES Branch
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Inspection Summary:
E Unit 1 Inspection on February 20-23,1979 (Report No. 50-352/79-02)
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Areas Inspected:
Routine, unannounced inspection by regional based
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inspectors of work activities and records associated with elecrical
and mechanical equipment, safety related piping, preservice inspec-
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tion.
The inspectors also reviewed licensee's action taken for NRC
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Bulletins and Circulars and performed a plant tour inspection.
The
Unit 1 inspection involved 114 inspector-hours onsite by four regional based inspectors.
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Results: Of the six arras inspected, no items of noncompliance were
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identified in four areat, two apparent items of noncompliance were g, -
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identified in two areas (Infractions - failure to follow procedures ! s
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for the storage of stainless steel pipe in laydown area - Paragraph 8; failure to follow procedure for drilling anchor bolt holes Paragraph 7).
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Insnection Summary
Unit 2 Inspection on February 20-23,1979 (Report No. 50-353/79-02)
Areas Inspected:
Routine, unannounced inspection by regional based inspectors of work activities and records associated with safety related piping activities and electrical equipment.
The inspectors also reviewed licensee's action taken for NRC Bulletins and Circulars and also performed a plant tour inspection.
The Unit 2 inspection involved 25 inspector-hours onsite by four regional based inspectors.
Results:
No items of noncompliance were identified.
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DETAILS 1.
Persons Contacted Philadelphia Electric Company
- J. Corcoran, Field QA Branch Head
- D. DiPaolo, QA Engineer
- J. Evans, QA Engineer
- G. Hutt, Office QA Branch Head
- G. Lauderback, QA Engineer
- D. Marascio, QA Engineer
- R. Mulford, Project Manager Bechtel Power Corporation T. Altum, Lead Welding Engineer R. Beech, Material Storage Engineer
- J. Blevins, QA Engineer A. Arch, Field Piping Engineer M. Dell Angelo, Instrumentation "aterial Fqineer
- B. Dragon, QA Engineer
- T. Fallon, Assistant Project QC Engineer
- R. Faust, Subcontracts Engineer
- H. Foster, Project QC Engineer M. Held, QC Engineer V. Jones, Senior Instrumentation Engineer J. Parham, Lead Instrumentation Superintendent
- J. R. Reiney, Project Construction Manager
- R. Sevo, Leau QA Engineer T. Stidham, Laydown Material Supervisor G. Zickefoose, Lead QC Engineer Nuclear Eneroy Services E. Labey, Leve'l II Examiner F. Carr, Level III Examiner (by': telephone)
Schneider Sheet Metal Company _
R. Lewis, QC Supervisor
- denotes those present at the exit interview on February 23, 1979 at the Limerick Site.
- denotes those present at the exit interview on February 2)f.
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1979 at the Philadelphia Electric Company corporate offi(e
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2.
Licensee Action on Previous Inspection Findings (0 pen) Unresolved Item (352/78-12-03):
Evaluation of ultrasonic indications found during preservice inspection of piping weld joints.
On January 9-10, 1979, weld RHD-047 was re-examine' and the results evaluated by the Nuclear Energy Services, Inc. (NES)
Level III, who determined that the original evaluation, documented on data sheet number 1566-38, dated December 27, 1978, was incorrect.
The inspector noted that the re-examination results and evaluation were documented on a second data sheet numbered 1566-38, dated December 17, 1978.
He requested that the original 1566-38 be marked "V0ID."
The licensee contractor representative stated that this would be done.
This item remains unresolved pending definitive action by the NES Level III to prevent the reoccurrence of inaccurate evaluation of indications by responsible NES (NDE) personnel.
(0 pen) Noncompliance (352/78-08-01):
The use of weld joint conf'gu-rations on the reactor building crane other than those specified on the design drawings. The licensae issued Nonconformance Report No.
3335 requesting P&H to review theic calcJlations and verify the adequacy of the 7/16" nominal fillet weld on the tie-plate to girder weld.
P&H stated, on SDDR 049422, that a 9/16" fillet weld is required on both sides of the plate to satisfy design requirements.
The reinforcement of these welds is complete.
The licensee has supplemented the Quality Control Inspection Report R-100 which now directs a surveillance inspection of welds be perfonned to assure completed work meets procurement documents.
This item remains open pending the completion of the licensee's internal inspection and evaluation of the box girder welds and reinspection by the NRC.
(Closed) Unresolved Item (352/78-12-01):
Identification and veri-fication of Engineering Change Notices (ECN's) on the PGCC/ACR equipment.
The inspector verified that the licensee maintains a listing of outstanding ECN's and Field Disposition Instructions in the central document control room's Master Parts Lists Manual (MPL).
The MPL maintains and up-dates the PGCC status through incoming correspondence from the supplier.
413 070
(Closed) Unresolved Item (352/79-01-03):
Electrical cables asso-ciated with the Power Generation Contro? Complex (PGCC) were not adequately protected.
The inspector verified that signs have been posted on the PGCC equipment and that wooden platforms have been laid over the structure to prevent stepping on cables.
The licensee has re-instructed the personnel working in the area as to the requirements that shall be maintained when performing tasks on the PGCC system.
(Closed) Noncompliance (352/78-09-04):
Failure to issue a Noncon-farmance and Disposition Report (N&D) for repair of HVAC Duct Section (Damper).
The inspector reviewed the completed M&D #35 which indicated that the repair by the site of five pieces (Piece Nos. 50, 71, 72, & 81) was unsatisfactory.
The items were returned to Schneider Sheet Metal factory for repair or replacement.
The inspector reviewed the contractors quality records Package No. 039-5 for the return to the site of the repaired pieces.
The inspector also inspected the installed dampers.
No items of noncompliance were identified.
(0 pen) Noncompliance (353/78-09-01):
Failure to perform inspection for design change which required the chipping of containment con-crete on Unit 2 to provide for seismic gap.
The inspector reviewed the licensee's action taken as stated in their response letter dated December 27, 1978.
The following documents were reviewed by the inspector:
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Job Rule C-2 (Revision 15) Page 1, Section 1.0, revised to incorporate the chipping of concrete in its scope.
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Job Rule G-5 (Revision 24) Page 15, Section 5.3, revised to describe a better procedure for the routing of field change requests.
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Field Inspection Report C-199-C-63-4, issued October 20, 1978.
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Field Change Request C-5111F, dated Novenber 6,1978.
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Field Change Request C-1397, dated January 29, 1979.
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Rework Notice C-932, dated October 20, 1978.
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The chipping work has been completed, however, the QC inspection found that for Unit 1, two locations do not meet the minimum 1" gap requirement and for Unit 2, four locations also do not meet the minimum 1" gap.
QC is awaiting engineering disposition for these measurements.
The QC group has reviewed approximately 50% of their representative sample (250-300) of Field Change Requests to assure that the modifications were inspected by QC.
The FCR review is scheduled to be completed in June, 1979.
This item is still considered open pending review by an NRC inspector, the resolution of the undersized gaps and the results of the QC review of FCR modifications.
(Closed) Unresolved Item (352/78-05-03):
Long-Tern In-Place Storage Environment was not implemented for Unit 1 RHR Heat Exchangers.
The licensee conducted an inspection of the RHRs (documented in PECo N-135, dated January 2, 1979) to determine if there were any deleterious effects resulting from removal of the nitrogen purge during the piping operations for a period of several months.
The inspection by the licensee did not reveal any deletericus effects.
Bechtel issued instructions (code #PFEM-784, dated October 17, 1978) for long-term storage.
The storage for the shell side of RHR heat exchangers is basically a wet-layup condition (filled with demineralized water with a 15% solution of hydrazine).
For the tube side a nitrogen purge is established.
A periodic maintenance activity has been established for the RHR.
The inspector reviewed the maintenance activity cards since this new long-term storage has commerced.
The inspector also inspected the RHR heat exchangers (A&B) in their storage condition.
No items of noncompliance were identified.
(0 pen) Noncomplicnce (352/78-04-03):
Failure to qualify contain-ment structural steel box bean weld joint.
The licensee stated that they have conducted post qualification weld tests for the weld joints shown in Details 4A and 9 on Bechtel Drawing 8031-C-875, Revision 7.
The tests were performed in accordance with Section 5 of AWS D.l.1 Code.
The Bechtel final test report for this qualifi-cation test has been submitted to PECo for their review and will be available for NRC review at a subsequent inspection.
This item is considered unresolved pending review of test report by an NRC inspector.
413 072
(0 pen) Noncompliance (353/78-05-01):
Failure to document an inspec-tion performed to verify that concrete strength met the design com-pressive strength requirements.
The inspector reviewed the licensee's corrective actions taken as stated in their response letter to NRC which was dated December 27, 1978.
The inspector reviewed the following documents:
Field Inspection Report (QC-G1-1):
This report states that
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based upon concrete cylinder reports and craftsmen time cards the concrete met the compressive strength requirements.
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Drawing C-637, Revision 8:
This drawing was revised to list what " guides" are mandatory and will require engineering approval for deviation.
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QC Checklist #15:
This list defines the mandatory inspection requirements of DWGS C-637, C-771, and C-772.
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Quality Control Instructions C-1.20 and C-1.40:
These docu-ments were revised to require use of checklist #15 and to identify the concrete placements which are related to the fuel pool systems.
During the review of the above documents, the inspector noted that Drawing C-771 (Revision 6), Design Change Notice #4 required temporary supports to be removed after a compressive strength of 3500 Psi is attained.
This differs from Drawing C-772 (Revision 6) and Drawing C-637 (Revision 8) which require a compressive strength of 5000 Psi.
The licensee stated that all drawings should have the same compressive strength.
The drawings will be revised so they are in agreement.
This item is considered to be unresolved pending review of drawing revision.
3.
Safety Related Comoonents - Review of Quality Records (Unit 1)
The inspector reviewed QC records associated with storage, instal-lation and maintenance of the Unit 1 Reactor Core Isolation Cooling (RCIC) pump and turbine.
The review was done to ascer-tain that periodic inspections were made during storage and after installation of the selected components, and that nonconforming conditions were properly disporitioned.
413 073
The inspector's review indicated that the required inspections were made on a periodic basis, nonconformance reports were issued as necessary and that the conforming conditions were properly dispcsitioned.
No items of noncompliance were identified.
4.
Preservice Inspection Activities (Unit 1)
The inspector interviewed licensee contractor personnel and reviewed documentation associated with evaluation of ultrasonic indications.
Nuclear Energy Services, Inc. (NES) Inter-Office Correspondence, Reference Number 5551-004H, dated January 24, 1979, and Bechtel Specification M-246A were examined by the inspector.
The inspecter questioned the applicability of acceptance and evaluation criteria delineated in the NES correspondence.
In a subsequent telephone conversation on March 5, 1979 with the licensee representative, the referenced criteria were determined acceptable and the inspector had no further questions concerning this matter.
No items of noncompliance were identified.
5.
Safety-Related Pipe Succort and Restraint Systems - Work Activities and Review of Records (Unit 1)
a.
Dynamic Pipe Supports (Installed-In-Progress)
The inspector visually inspected three mechanical snubbers (arrestors) to the latest drawings at the time of the inspec-tion.
The snubbers were installed in systems in progress.
The mechanical snubbers were examined for deterioration, cor-rosion, deformation, fastners, obstructions, and clearances.
The following mechanical snubbers, as designated by drawing number, were examined:
Support (Revision)
Type Load Pounds Stroke-Inches HBB-ll8-H38(2)
PSA-10 3821
EBB-108-H19(0)
PSA-3 655
HBC-147-H6A(2)
PSA-3 2031
413 074
The bolted connection between the snubber HBB-ll8-H38 housing and extension piace has bolts that remain to be checked for torque and staking.
Snubbers EBB-108-H19 and HBC-147-H6A have similar bolting that remains to be checked for torque and to be lock wired.
The inspector reviewed engineering control list for checks on installed snubbers for the problems identified (Reference " Snubber Inspection" PFEM 889). All three snubbers were listed.
It_ appears that the licensee has control over this item.
This item is related to a previous inspection finding (352/78-06-01) which was also addressed in IE Report 50-352/78-10, Paragraph 6 of the Details.
The inspector reviewed QCI P-210, Activity No. 3.2.2, Revision 5, January 25, 1979 which addresses QC verification of securing mechanical connections.
The inspection implementation remains to be verified and will be re-addressed by the NRC inspector under Unresolved Item (352/78-06-01).
Snubber EBB-108-H19 was tagged for undersized welds and documentation was traced to NCR 3449 which lists this discrepancy.
This NCR also required a check on "all around" welds where meeting material sizes were such that there was not space for a fillet weld.
The inspector independently identified a similar condition on snubber HBC-147-H6A, located at the clevis connection.
This is an unresolved item pending licensee \\s completion of engineering review and corrective action (352/79-02-01).
No items of noncompliance were identified.
b.
Pipe Component Support Structures The inspector visually examined three pipe support systems to the latest drawing revision at the time of the inspection.
The systems were in progress of installation.
The pipe component support structures were examined for orientation, acceptat;le welds, lubricants where applicable, naterial as specified by drawing and bolting requirements.
The following systems, as designated by drawing number were examined:
Support (Revision)
Type HBD-69-H10(5)
Vertical Restraint HBC-138-H8(3)
Double Box HBC-147-H6(1)
Restraint Al3 075
The brace support (f tem 7) for hanger HBD-69-H10 has a weld on the obtuse angle (approximately 1500) which is questionable as to meeting a fillet weld criteria.
This item was discussed with the Bechtel pipe hanger engineer.
The licensee has a similar documented concern (Reference PECo Finding Report N-139, Engineering Question) which addressed an acute angle weld.
Inspection Criteria for these welds, designated by drawing as equal angle fillet welds, remaus to be specified.
This is an unresolved item pending engineering review and action (352/79-02-02).
No items of noncompliance were identified.
c.
Review of Records The inspector examined documented records of four dynamic pipe supports and four fixed pipe supports.
The records were examined for support classification and type; QA/QC verification of support location, designation of weld loca-tion; weld material identification; and, welder qualification.
The applicable records for the following pipe support systems were examined:
prawing No. (Revision)
Drawing No. (Revision)
HBB-ll8-H38(2)
HBB-ll8-H15(4)
EBB-108-H19(0)
HBC-138-H8(3)
HBC-147-H6A(2)
HBC-147-H6(1)
HBC-148-H40(1)
GBB-ll6-H5(5)
The inspector examined the pipe support drawings and the following records to validate the existance of attributes stated below:
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QCIR M51-HBB-118-5-8, March 14,1978
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QCIR M51-HBB-118-3-5-1, March 2,1977
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QCIR M55-EBB-108-5-1, March 22,1978 413 076
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QCIR M55-EBB-108-2-5-1, March 3, 1977
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QCIR Mll-HBC-147-5-ll, August 23, 1978
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QCIR Mll-HBC-147-1-5-1, January 25, 1977
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QCIR Mll-HBC-148-5-3, April 12,1978
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QCIR Mll-HBC-148-5-1, January 26, 1977
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QCIR M51-HBB-118-5-2, November 23, 1977
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QCIR Mll-HBC-138-5-2, September 8, 1977
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QCIR-M11-HBC-138-1-5-1, January 25, 1977
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QCIR M207-HBC-5-2, May 11, 1976
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QCIR M51-GBB-ll6-5-6, September 15, 1977
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QCIR M51-GBB-ll6-1-5-1, January 26, 1977 The Filler Metal Withdrawal Authorizations, form WR-NC-2 were found included in the welding QCIR packet.
The inspector examined documented qualification records for seven welders assigned to the above supports.
The records included a check by QC for support location and support interference.
Completed record for these attributes exists for support HBC-147-H6.
These attributes remain to be checked for the remaining seven supports.
The records have not been finalized but do require QC fine.1 validation for location and interference.
The inspector has no further questions on records at this time.
No items of noncompliance were identified.
6.
Refueling Floor Structural Steel - Work Activities (Units 1 and 2)
The inspector interviewed licensee personnel, examined records and inspected tagging requirements for the test equipment used for erection of structural steel at the 352' level.
A sample of receipt inspection, testing, and inspection records were examined.
Records for the qualification of the QC inspector was also examined.
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413 077
The inspector considered the above item with regard to the following:
Bechtel Specification 8031-C41 A, revision 6; Bechtel Specification C-63; Bechtel Specification C-72; AISC Manual of Steel Construction, seventh edition; QC Instruction 8031/R-1.00 (Revision 10)
The following documents were reviewed with respect to the above attributes:
QCIR-C-41A-MRP,-30094, March 27, 1976, Load Washers
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NCR 1597 - Washers - Load Indicator Washers
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Certification for A325 Washers (MRR-30094)
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QCIR-C-41A-MRR-30100, Load Washers, with Certifications for A490 Washers
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Field Inspection Report dated May 4,1978 - Specific to Load Indicator Washers and Trace of Torque Testing Device C-327
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Field Surveillance Inspection Report - Plan #C-211-C63-1, Dsg C-211 and FSIR C-212-C-63-1, Dag C-212
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Training and Certification Records for a QC Engineer No items of noncompliance were identified.
7.
Plant Tour (Units 1 and 2)
The inspectors toured the Uni's 1 and 2 containment and reactor buildings observing work in-progress, in-place storage practices, area cleanliness, cod completed work.
He discussed the technical aspects of the work in-progress with the construction craftsmen, iupervisore, and quality control personnel.
The following items were iden'.ified during this punt tour inspection:
a.
The reactor building columns E-17, Unit 1, and E-26, Unit 2, were observed to contain what appeared to be unconsumed tack welds.
These tack welds were in the cover plate to flange welds and had varying degrees of undercut, lack of fusion, and overlap.
The licensee issued Finding Report N-149 whi(.h recommends further inspection and repair.
This item is unre-solved pending completion of the licensee's inspection and corrective activities (352/79-02-03 and 353/79-02-01).
413 079
b.
The inspector observed that craftsmen were drilling 3/4" holes in a concrete wall (elevation 182'-10") of the RHR room "A",
in Unit 1.
There were two holes intersecting each other.
Upon further investigation, the inspector noted that the deeper of the two drilled holes had contacted reinforcing steel and was abandoned.
The inspector reviewed the design criteria for drilling new holes after abandoning the original hole.
Bechtel Drawing C-603, Revision 26, entitled " Typical Concrete Embedment Details" requires that the following be adhered to after abandoning a hole requiring replacement.
Abandoned hole shall be filled with Dry-Pack mortar
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New holes shall be drilled no closer than one hole diameter from the center of filled hole New hole shall be drilled after mortar has reached the
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strength of the original concrete The inspector informed the licensee that none of the above design requirements were adhered to and this was contrary to Criterion V of 10 CFR 50, Appendix B (352/79-02-04).
8.
Reactor Coolant Pressure Boundary and Safety Related Pioe Nelding -
Observation of Work (Unit 1 The following listed activities were observed and verified to be in accordance with selected portions of the ASf1E III and IX codes, the Quality Assurance Manual ASf1E Section III, Specification P-301, and regulatory requirements:
Observed the welding of the intermediate passes on the 24"
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diameter, nuclear class 1, feedwater pipe joint DLA-105-1/ll FW3. Verified the weld identificati' n, proper weld procedures, the welders qualification, the interpass temperature, the weld deposit, and evidence of quality ccatrol checks.
Observed the intermediate weld passes on the 14" diameter,
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nuclear class 1, HPCI pipe joint EBB-129-3/13 FW3.
Verified the same attributes as the preceeding weld.
Observed the fitup, alignment, and welding of the root pass on
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the 24" diameter, nuclear class 1, feedwater pipe joint DLA-106-1/10 FW3.
Verified the weld identification, weld procedure, welder qualification, appearance of the weld, welding materials, and quality control checks.
No items of noncompliance were identified.
413 079
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The out door pipe storage laydown area was inspected to verify compliance with the Bechtel Job Rule for Storage and Maintenance of Fabricated Piping and In-Place Storage Maintenance of Small Manual Valves, JR-G-8.
Much of the laydown area was covered by several inches of snow which-did not allow complete assessment of the carbon steel pipe uncapped, free draining practice.
It was apparent that most of the carbon steel spools had been positioned to promote drainage.
Two spools appeared to have questionable slopes, HBB-717-4-3 and GBB-213-1-4 Two stainless steel pipe spools, DCA-105-1-2 and DCA-105-1-4, were observed to be uncovered and uncapped.
The Job Rule, JR-G-8, requires that stainless steel pipe spools are to be laid down in locations not subject to rain, snow, sleet, and shall be covered.
End caps shall remain in place.
Review of the storage inspection records verified that surveillance inspections are being conducted as required by the job rule.
The pipe spools were received in storage on July 28, 1978, and placed in the laydown area on October 26, 1978.
The failure to properly store and maintain the nuclear class 1 pipe spools in accordance with procedures is an item of noncompliance (352/79-02-05).
The inspector examined the installation activities and controls for buried RHR Emergency Service Water piping HBC-176-C1081-5 and 6.
He examined the condition of the pipe coating and the administrative precautions employeed to assure its integrity.
He verified that selected portions of the specification C-9, Installation and Testing of Underground Piping, are being implemented.
No items of noncompliance were identified.
9.
Reactor Coolant Pressure Boundary and Safety Related Pipe -
Review of Quality Records A review of 3 pipe spool quality assurance document packaaes was performed to verify compliance with the specification P-312, the ASME III Code, and regulatory requirements.
The following pipe spool document packages were reviewed:
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Pipe Spool Size Nuclear Class HBB-127-1-2 24"
EBB-129-3-2 14"
DCA-105-1-2 24"
The documents reviewed consisted of the material test reports, shop fabrication records, and inspection and receiving records.
No items of noncompliance were identified.
10.
Reactor Protection Systems The inspector examined the storage control of the Pressure and Differential Transmitters and the seismic acceptance test data associated with these transmitters.
The transmitters are stored in accordance with the requirements of Specification No. 8031-M-206, Revision 2, dated April 28, 1978.
The maintenance storage activity cards list the specification (M-206) requirements and were verified by the maintenance engineer.
The seismic Repcrt No. 43082-1 meets the requirements of specification M-206 and was approved by engineering on November 21, 1977.
The transmitters were qualified and mounted as described t,elow on a multiaxis test table.
The test were based on a multiple-frequency input as referenced in IEEE 344 1975, Paragraph 6.6.3.
The model 1151 transmitter was mounted on a Rosemount Bracket and the model 1152 transmitter used a rigid Wyle-fabricated bracket.
The fixture design is identified in the reference Wyle test procedure.
The inspector verified by performing a data review of the test documentation, which formed a part of the receiving package of the transmitters, that the burn-in and performance test data meets the requirements of specification M-206 and performance procedure
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The chloride content of the transmitters was verified in Test Procedure 12727B data, which also formed a part of the receiving data package.
No items of noncompliance were identified.
AI3 081
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11.
IE Bulletin and Circular Followup (Units 1 and 2)
a.
The IE Bulletins discussed below were reviewed to verify that:
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Licensee management forwarded copies of written response to appropriate management representatives.
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Corrective action taken by the licensee was as described in the written response.
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Information discussed in licensee's response was suppo:ted by records.
The licensee's reply was prompt and within the time
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period described in the Bulletin.
Bulletins 75-03 ASCO solenoid valves.
Licensee letters dated April 12,1978, No. 034258, defined action that was taken to support the design change.
This bulletin is closed but continued action is being taken under Bulletin 78-14.
77-08 Assurance of Safety and Safeguards During the Emergency-locking Systems.
The licensee has con-sidered this task as part of their " Limerick Facility Plan" and a review of this plan considers the Bul-letin concerns.
Reference Licensee Letter dated February 23, 1978.
77-05 &
Electrical Connector Assemblies.
The licensee has77-05A reviewed the data associated with the items used at Limerick 1 and 2 and have sufficient data on their connectors to assure operation during a LOCA.
77-07 Containment Electrical Penetration Assemblies at Nuclear Power Plants Under Construction.
The licensee's review of their penetration design indicates that the problem identified in Bulletin 77-07 is not
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applicable to their configuration.
AI3 062
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78-06 Cutter Hammer Type M Relays with D.C. Coils.
The licensee has reviewed their electrical design and replaced identified relays with other units.
Reference letters of June 20, 1978, July 12, 1978, and Septem-ber 11,1978.
78-10 Corrosion of Bergen-Paterson Hydraulic Shock Supressor Accumulator Spring Coils.
The A/E (letter Code BLP 17392) states that only mechanical snubbers are to be supplied for LGS units, however, to-date the NSSS has not pi ced a purchase order for snubbers.
The licensee has informed the NSSS that they do not want hydraulic snubbers for Limerick Units.
The inspector informed the licensee that this item will be reviewed again to verify that the NSSS supplied mechanical snubbers for Limerick Units, b.
IE Circulars discussed below were reviewed to verify that they had been reviewed for applicability by cognizant manage-ment, and appropridte action initiated.
Circulars 77-04 Inadequate Lock Assemblies.
The licensee initiated action to review requirements for lock assemblies in their letter of February 22, 1978.
77-05 Fluid Entrapment in Valve Bonnets.
The A/E recom-mended to licensee solutions to tne problem in their letter (Code BLP 16389).
The licensee is in the process of drafting a reply to this letter of recoa-mendation.
This item will be reviewea.,y the NRC inspector in a subsequent inspection.
77-08 Failure of Feedwater Sample Probe.
This Circular was not sent to Limerick, but PECo received it frcm their Peach Bottom Facility.
The licensee has requested Bechtel on July 10, 1978 to review this Circular and determine what action has to be taken, i f any.
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77-11 Leakage of Containment Isolation Valves with Resilient Seats.
The records reviewed by the inspector indicated that the isolatiori valves are supplied from BIF Cor-poration and the seats are viton material, whereby excessive leakage has not been a problem.
77-12 Dropped Fuel Assemblies at BWR Facilities.
The inspec-tor reviewed NSSS letters dated October 31, 1977, November 14, 1977, and November 29, 1977, which addressed this Circular.
The NSSS listed several design improvements in Limerick's refueling plat-forms and fuel grapples to preclude the dropping of fuel assemblies.
77-13 Reactor Safety Signal Mcested During Testing.
The licensee has issued a memo to the operating personnel for consideration of this item during testing.
77-14 Separation of Contamination Water Smtems From Non-Contaminated Plant Systems.
Tha inspector reviewe1 an A/E letter (Code BLP 16230) which stated that their design for Limerick doesn't allow for any interconnections between domestic or contaminated water systems.
78-02 Proper Lubricating Oil for Terry Turbines.
The licensee issued instructions to Mobil Oil Corpora-tion (developer of Limerick's Lv' rication Program)
a that they list Mobil RL-851 (vaportec light) for all the Terry Turbines.
78-03 Packaging of Greater Than Type "A" Quantities of Low Specific Activity Radioactive Material for Transport.
The 'imerick Plant Superintendent issued a directive, dated Juna 8,1978, to operating personrel to comply with Part 71, Packaging Require-ments, ahen Limerick becomes operational.
Reference memo issued December 15, 1977.
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78-04 Installation Errors That Could Prevent Closing of Fire Doors. A review of the licensee designs indicate that they do not have the horizontal sliding fire doors.
Reference document control form No. 037871 dated May 23, 1978.
78-06 Potential Common Mode Flooding of ECCS Equipment Rooms at BWR Facilities.
The licensee has requested an evaluation of their design.
Reference letter dated December 4, 1978, PLB 8802.
78-07 Damaged Components of Bergen-Patarson (B-P) Hydraulic Test Stand.
Licensee's memo of July 14, 1978 stated that hydraulic snubbers are not used and therefore, there will be no B-P test stand for Limerick Station.
78-08 Environmental Qualification of Safety Related Equip-ment at Nuclear Power Plants.
The licensee has taken action to review the environmental qualifica-tions of electrical equipment for Limerick 1 and 2.
Reference letters of October 25, 1978 and November 15, 1978.
78-09 Arcing of GE NEMA Size 2 Contactors.
A review of the contactors used at the Limerick 1 and 2 site indicates that the NEMA Size 2 item in Circular 78-09 is not used in the electrical equipment.
Reference letter of September 22, 1978.
78-11 Recirculation Motor-Generator Overspeed Stops Set Incorrectly.
The inspector reviewed a GE letter, dated September 14, 1978, which outlines three specific items which should preclude the overspeed stops from being set incorrectly.
78-12 HPCI Turbine Control Valve Lift Rod Bending.
The inspector reviewed a GE letter dated July 19, 1978, which stated that two field disposition instructions were issued (#46/73030 for Unit 1 and #26/73030 for Unit 2) to modify the linkage to reduce the bending moments on the lift rods.
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78-13 In Operative Service Water Pumps Due to Ice Clogging.
Licensee's OA department recently con-ducted an audit (#198) of Circulars and Bulletins and one of their findings was that this Circular required further action by PECo.
The f!RC inspector will review licensee's actions taken for this Cir-cular at a subsequent inspection.
78-14 HPCI Turbine Reversing Chamber Hold Down Bolting.
The inspector reviewed documentation which stated that two fiSSS Field Disposition Instructions (#54/
73030 and 32/73030-2) were issued to modify the bolting design on the Limerick Terry Turbines.
78-15 Anchor Darling Tilting Disc Check Valve Failed to Close Due to Improper Orientation in Pipe Line.
The inspector reviewed documentation which stated that there was only two valves of this type purchased for Limerick.
These valves are to be used in the spray pond pump house and will be installed correctly (horizontal position).
78-16 Limitorque Type SMB Valve Actuators Fail to Function Due to Excessive Clutch Wear.
The inspector reviewed various documents concerning this problem per flSSS supplier.
This is not a generic problem with actuator but failure due to improper operation of actuators and therefore, specific instructions are required for instructing personnel on the proper use of valve actuators.
PECo letter dated January 5, 1979 from Superintendent of Limerick Station listed six reconmended measures that are to be followed to prevent failures.
78-18 UL Fire Test.
The licensee has taken action to investigate the concept of Circular 78-18.
Reference letter of February 6, 1979, fio. 048982.
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12.
Unresolved Items Unrasolved items are matters about which more 'information is required in order-to ascertain whether they are acceptable items, items of noncompliance, or deviations.
Three unresolved items disclosed during this inspection are discussed in Paragraphs 5 and 7.
13.
Fxit Interview The inspectors met with licensee representatives (denoted in Para-graph 1) at the conclusion of the inspection on February 22 and 23, 1979. The inspectors summarized the purpose and the scope of the inspection and the findings.
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