IR 05000320/1977012
| ML19220B632 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/04/1977 |
| From: | Fasono A, Mccabe E, Rebelowski T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220B630 | List: |
| References | |
| 50-320-77-12, NUDOCS 7904270149 | |
| Download: ML19220B632 (15) | |
Text
'.
-
-
,
-
Reg I Form 12 (Rev Feb 77)
U. S. NUCLEAR REGULATORY COMMISSION
.
OFFICE OF INSPECTION AND Ef2FORCEMENT
REGION I
IE Insoection Report No:
50-320/77-12 50-320 Docket No: _
Licensee:
Metropolitan Edison Company License Ho:
CPPR-66 Box 542 Priority:
--
Reading, Pennsylvania 19603 Category:
B Safeguards
--
e wn, ennsyhania W-2)
MW Location:
,
Type of Licensee:
2772 m (B M Routine (Unannounced)
Type of Inspection: __
Dates of Inspect 9 s:
March 28-31,1977 Da i of r eviou Inspection: March 21-23,1977 Reporting Inspector: 8k
'
J b4rw 1,/f27 T. Reb owpi, Reactor inspector TE '
~
'
Accompanying Inspectors:
e e*+ d
-
~
- m 2
/+ 77 A. Fasano, Reactor Inspector
_
FATE l
'
'
t DATE
-
DATE DATE Other Accompanying Pernnnel:
None DATE
-
Reviewed By: ___~ f. McCabe, Jr., Chief, Nuclear Support Section #1
%
/ 77 (.
i DATE
~
dctor Operations & Nuclear Support Branch 80 343 t
7904:d701H
-
.. - -
l
-
-
-
,
SUMMARY OF FINDINGS _
.
Enforcement Action None Licensee Action on Previous j Identified Enforcement Items
.
Not inspected.
Reportable Occurrences _
None identified.
f Other Significant Findings _
J Current Findings A.
_
Acceotable Items _
1.
These are items which were inspected on or Unresolved Item (except as noted).
(Details 2.a and c)
IE Bulletin / Circular Followup.
t a.
(Details 3)
Test Program Implementation.
b.
(Details 4.a. b(1) and b(3))
Test Frocedure Review.
c.
(Details 5)
Remote Shutdown capabilities.
d.
(Details 6)
Reactor Co31 ant Loop Hydrostatic Test.
c.
(Details 7)
Test Procedure Verification.
f.
2.
Unresolved Items These are items for which more informatio
,
compliance.
i
-
.
l l' ~
-~..,
..
.
..
.-
-..
..
_ __ _
_
_
.
77-12-01 OperationsBulletin 74-08 - Corrective Action TMI-2.
In-complete.
(Details 2.b)
,
77-12-02
-
Nuclear Chemical Addition and Sampling System Operational Test.
(Details 4.b(2))
3.
Open Items During the review cf the " Draft" Procedure 200/4 the following concern was identifi M :
Open Item 77-12-03.
Evaluation of NOT techniquer for iden-
{
tification of leaks.
(Details 6.a(4))
B.
Status of Previously Identified Unresolved Items Not inspected.
I Management Interviews An entrance interview was conducted with Mr. R. Toole, Test Superintend-ent on March 28, 1977. The scope of this inspection and regjired per-sonnel contacts were discussed.
-
An exit interview was conducted on March 31, 1977, at the completion of the inspection. The persons listed below were attendees:
General Public Utilities Service Corporation Mr. M. Nelson, Technical Engincer Mr. J. Stromberg, Chief Auditor Mr. R. Toole, Test Superintendent The following items were discussed at the exit interview:
A.
IE Bulletin / Circular Followup.
(Details 2)
B.
Test Prograra Implementation.
(Details 3)
C.
Test Procedure Review.
(Details 4)
D.
Initial Startup Program - Remote Shutdown Capability.
(Details 5)
(
-.
80 245
.
..
.
.
.
.
..
.
.
-
.
E.
Reactor Coolant System Hydrostatic Test.
(Details 6)
F.
Test Procedure Verification.
(Da. tails 7)
G.
Plant Tour.
(Details 8)
i
.
.
A.
80 34G
-
.
=
me+ m
_
-
_
DETAILS 1.
Personnel Contacted General Public Utilities Service Corporation (GPl!SC)
.
_
Mr. J. Barton, Startup and Testing Manager Mr. R. Fenti, QA Auditor
'
Mr. T. Hawkins, Assistant Startup Test Superintendent Mr. S. Levin, Project Engineer Mr. M. Nelson, Technical Engineer Mr. J. Stromberg, Chief Auditor Mr. J. Toole, Test Superintendent Mr. J. V.19.+., Site Quality Assurance Manager Mr. J. Ulrich, Startup Test Engineer United Engineer and Constructors, Inc. (UELC)
Mr. B. Bozarth, QC Engineer Mr. R. Dourte QC Engineer Mr. J. Lambert, Field Supervisor QC
!
Mr. D. Rhyme, Lead Mechanic 1 Engineer
.
Metropolitan Edison Company
.
Mr. J. Seelinger, Unit 2 Superintendent, Technical Mr. W. Sawyer, Engineer 2.
IE Bulletin / Circular Followup IE Burietin/ Circulars discussed below were revicwed te verify that:
Licensee management forwarded copies of the response, where
{
--
responses were required, to the bulletin / circular to appro-priate onsite management representatives; Infoimation discussed in the licensee's reply and/or action
--
was supported by discussions, facility records or by visual examination of the facility; Corrective action taken was effected as described in the
--
reply; and, i
a
\\
_
80 2n
.
a,
,e
,
_
._
_
The licensee's reply was prompt and within the time period
--
described in the bulletin / circular.
The review. included discussions with licensee personnel and obser-vation and review of items discussed in the details t"r.
The licensee's actions and response concerning IE Bulletin / Circular followup were acceptable.
Additional action required by the licen-see are noted as unresolved items,Bulletin 75-06 - Defective Westinghouse Type OT-2 Control a.
Switches.
Reference: Bulletin No. 75-06, May 30,1975; Licensee's Response dated July 25, 1975.
i This bulletin deals with a spring return-to-neutral switch having an internal spring force return to the neutral position that is defective.
The switch is a Westinghouse Type OT-2.
Westinghouse reported that internal friction forces caused some switches to bind and fail to return to the neutral position.
l The licensees response indicated that this switch is not in-stalled or planned to be installed in Unit 2 equipment. The inspector checked similar type switches in the control room and found the General Electric type installed as stated by the licensee. Westinghouse switches located in the power cabinet in the contrei room were not OT-2 type switches.
A check was also made in the Diesel Generator room at panel CP 308 and the 2DG-1 panel.
The Westinghouse switches in these cabinets were not the OT-2 type.
This item is closed.
b.
Bulletin 74-08 - Deficiency in ITE Molded Case Circuit Break-ers, Type HE-3.
Reference: OperationsBulletin 74-08, July 31, 1974; Licensee's Response dated August 22, 1974.
This Bulletia describes a deficiency associated with the mag-netic trip elements in the ITE Type HE-3 molded case circuit breakers, current rating of 20-90 amperes. The pickup points for the magnetic (instantaneous) trip elements are substan-tially higher than the published ITE time current curves for the breakers. The deficiency was discovered during preopera-tional testing at the Trojan Nuclear Power Plant.
(
i 80 248
-
-
_
e
.
_
__
_
The licensee's response indicated that Type HE-3, rated at 25 and SG amperes are installed in Unit 2 equipment, and that the preoperational testing results will be available for review. Should similar circumstances exist for the installed breakers, corrective action will be initiated with the intent to complete the Bulletin action requested and review for acceptance prior to initial fuel loading.
The inspector reviewed Problem Report GPU No. 2145, 480 Volt MCC (ITE) HE Breakers, March 15, 1977 and GPU Seevice Corpora-tion Memorandum, February 21,1977, TMI-II-4928.
The above referenced documents indicate that testing of the ITE-H3 breakers, during the preoperation phase of Unit 2, indicates that problems with the ITE-HE3 breakers at Unit
2 exist as identified by Bulletin 74-08.
The testing of 207 l
,
breakers has resulted in 127 breakers having the deficiency.
Corrective actions remain to be taken by the licensee. This is unresolved item 77-12-01 pending completion of breaker identification and breaker replacement with satisfactory test data. Also, it is understood, from the licensee's August (
22, 1974 response, that corrective action will be completed prior to initial fuel loading.
!
c.
Circular 77-02A - Potential Heavy Spring Flooding.
Refer-
!
ence: IE Circular No.77-02A, February 18, 1977. No licen-I see written response is required.
This circular was provided as information to the licensee.
Discussions with cognizant personnel indicated to the inspec-tor that the licensee was knowledgable of the potential for flooding and was in contact with the weath: bureau. Actions
.
were taken to move aquipment to areas less subject to flood.
!
The data available to the licensee indicated that flooding was unlikely but precautionary measures were taken. The potential for flooding as described in the circular no longer
{
exists.
!
!
This item is closed.
\\_
.80-349'
.
,
.
-
-
.
3.
Test Program Implementation _
The test program was reviewed to verify by interview of the Test Program Director and the Test Superintendent that these key in-dividuals are familiar with the test program.
'
It was verified that the following is understood:
.
Responsibilities of key personnel.
--
Method and responsibility for appointing test personnel.
--
'
Lines of authority and responsibility.
--
Organizational interfaces for organizations involved in the
--
test procram.
In parallel with the interviews, the inspector reviewed the Organ-izational Chart; the Test Manual, Revision 5 July 13,1976; the Test Plan for March 29-Aoril 4; the Test Work Group (TWG) minutes-file 402 for March 17, 1977; the QC Phase 1 Exception Item for (
Turnover Package NR-111, Job No. 9459-02, March 19,1976, and the current extracted Critical Path itens schedule.
The Test Superintendent and separately the Startup Testing Manager were interviewed.
Based on the interviews and inspection of management control documentation, the inspector verified that the Test Superintendent and Startup Testing Hanager are familiar with the test program and are aware of their responsibilities in the conduct of the Test Program.
A review of the Test Manual, Revision 5, July 13,1976 we made and used as faces for program knowledge.
The purpose of the test manual is to provide policies, procedures and instructions for the administrative control of the test program at TMI-2.
A review of a copy ;f the Test Plan docusent for the period, March 29, 1971 through April 4,1977 was made.
This document reflects the plans for the week.
The document contains lined out items to reflect the accomplishment of tne past week coupled with hand written notes.
The typed items are items new and old that require attention. The dicument reflects the major milestones, plant conditions and tests authorized to be performed.
(.
..
i 80~350
.
.
-
-
~
.
A review of the QC Phase 1 Exceptions Items for Package NR-111, Job Nc. 9459-02, March 19, 1976 shows a sample of items that must be considered before testing. The exception list contains the deficiencies that were considered prior to testing the Nuclear River System. The Test Superintendent can reject acceptance for testing by use of a speed letter specifying those items required to be corrected prior to acceptance for +x ting.
The inspector confirmed the conduct of interface group meetings by reviewing File 402.
This file contains the " Unit 2 Test Work-ing Group Meeting Minutes". Meeting minutes for March 17, 1977, Meeting #54 was reviewed.
The TMG is composed of GPU, B&R, Met Ed and B&W representatives. The minutes indicate approval of procedures, final approval of test results and final approval of Test Change Notices.
Based on the interviews and the review of program documentation,
.
the inspector has no further questions on this item.
4.
Test Procedures Review The Office of Inspection and Enforcement (IE) Preoperational a.
Inspection Program dealing with Test Procedure Review has the objective of reviewing safety related tests for consis-te*ity with regulatory requirements, guidance and license commitments.
Uniform criteria are applied i'i the test procedure review to assure the technical and admitiistrative adequacy of the pro-cedures. This program is a sampling program which is an ongoing effort conducted prior to the perfomance of said tests and prior to issuance of aa operating license.
b.
The following approved tests were reviewed:
TP 305/2, Reactor Protection sponses.
.
TP 600/5, Nuclear Chemic.1 Addition and Sampling ?ystem Operaticnal. Test.
.
TP 120/5, Spent Fuel Handling Bridge Functional Tast.
TP 120/6, Main Fuel Handling Bridge Functional Test.
TP 120/7, Auxiliary Fuel Handling Bridge Functional Test.
(
'
80 351
.-
,
.
-
-
Tn. Test Procedures were reviewed for the following:
Management Approval;
---
Appropriate committee review;
---
--- Procedure format;
--- Test objective clearly stated; Prerequisites specified;
---
Special environmental conditions;
---
Acceptance Criteria;
---
Source of Acceptance Criteria;
---
Specified tett conditions;
---
Signature and dating for test conduct;
---
\\
Provisions for Noting deficiencies;
---
Restoration of connections, disconnections and jumpers;
---
Provision for noting personnal conducting and evaluating
---
test lita; Eler ?*ical and control requiremeni;;
---
Temporary Installations;
---
References to FSAR Sections; and,
---
Step-by-step instructions assuring that test objectives
---
are met.
(
8 0 2.5 2
-
,
_
.
.
.
(1) TP 305/2, Reactor Protection System Resoonse Time The purpose of this test is the following:
To measure the time between a specific step change
---
in simulated sensor input to each Reactor Protection System, RPS, trip channel, causing the associated trip bistable to pass from a non-tripped to a tripped condition and the loss of output voltage from the tripping of the 2 out of 4 trip logics; To verify that each RPS trip bistable trips its
---
associated RPC channel trip module; To verify that each shutdown by-pass key switch
---
performs its by-pass function correctly; and, l
To verify that each channel by-pass key switch
---
performs its by-pass function correctly.
The procedure addresses the nuclear instrumentation and the electronics response time for the protection channels.
- With respect to the simulated signal pickup to the trip actuation time measurement, this procedure provides for the response time values.
The inspector reviewed the following docuraents along with the review of this procedure:
.
I FSAR Section 7.2;
---
Test Manual, Revision 5, July 13,1976; and,
---
FSAR Supplement 3, Table 22.29-2, AM, 50.
!,
---
I Based on the review of the above and discussions with the i
licensee, the inspector has no further gaestions on this item at this time.
!
.
i
[
t i
80 253
.
.
.
-
,
(2) TP 600/5, Nuclear Chemical Addition and Sampling System Operational Test The inspectors review of TP 600/5 indicated the following areas of concern:
The method of determing maximum allowable flows of
-
sampling system vs. secondary coolant temperature is not ad'ressed in Paragraphs 9.2.2, 9.1.2, and 9.2;
-
Paragraph 9.6.2 does not address hold time prior to determining precipitation; and, Paragraph 9.6.1 shall include 0.P. number as a
-
reference.
The licensee has agreed to review these areas of concern.
Pending completion of inspector review of licensee actions to resolve addressed concerns and verification of actions at a subsequent inspection, this item remains
!
unresolved (77-12-02).
(3)
Additicaal Test Reviews The inspector did not identify any inadequacies in the following procedures:
TP 120/5, Spant Fuel Handling Bridge Functional Test; TP 120/6, Main Fuel Handling Bridge Fun ^ional Test; and, TP 120/7, Auxiliary Fuel Handling Bridge Functional Test.
5.
Initial Startup Proaram to Demonstrate Renote Shu+.down Capability Reference: Regulatory Guide 1.68.2 Ti inspector reviewed the licensee's impletentation of a preopera-twnal pregram to demonstrate the ability to shutdown and cooldown renotely outside the control room.
(
80 354
-
I
.
-
.
-
-
,
The licensee has scheduled a test SP 600/36, Practice Run for Shutdown from Outside the Control Room.
The objectives of the procedure is to verify that plant instrumentation and control for systems required for remote shutdown have been completed and operabl e.
o ior to initial fuel loading, during the Hot Functional Testing, r
the preliminary test to verify the Operational Procedure OP 2202-1.10 to maximum extent dependent on completion of systems (excep-tions could include the inability to run Main Feed Pumps, Absence of CRDM's and steam generator levels may not be varied).
The testing will demonstrate controls during a steady state condition and during a cooldown of reactor coolant system.
Remote shutdown testing at >10% power will be performed in TP 800/26, Shutdown from Outside the Control Room during Power As-cension Testing.
6.
Reactor Coolant System Hydrostatic Test - Quality Control Participation Reference: Proposed Draft of MTX 147.5, Reactor Coolant System Hydrostatic Test The inspector discussed with the Quality Control Field Inspection personnel their support and coverage of defined areas during the initial hydrostatic test of the Reactor Coolant System and asso-ciated support systems.
The areas of concern that were addressed and commented on by the licensee included:
a.
Method of assuring that all welded joints and mechanical connections have been uncovered and cleaned prior to inspec-tion daring testing.
The licensee stated that within the test boundaries, the sub-systems under test will be identified.
The assigned inspec-tion team for each subsystem, after test briefing and review of isometrics will walk down assigned systems under Quality Control Inspection personnel to ensure location and physical condition of the inspected areas.
\\
80 255 f
.
l
-
.
g
,-
_
..
.
b.
The inspector requested that a set of isometric drawings be available for review at time of testing.
The licensee stated that isometrics will be available on site.
The inspectors concern on mannar of inspection of piping and c.
documentation was answered by ' licensee as indicated below:
(1) The licensee stated that due to thc elevated tempernture of system (250" F) during testing additional scaffolding may be installed; (2) Standby personnel will be availabel if members of desig-nated inspectir,e teams are absent; and, (3)
All informaticr from inspection teams will be coordinated by the Quality Control Engineers and recorded as satis-factory in the Test Procedure af ter a review by the Test Engi,eer.
This review of data will be conducted at each pressare plateau and exceptions to the criteria will be reviewed by Test Working Group.
i d.
The inspector requested the licensee to evaluate their method of visually observance of leaks.
Due to the elevated temper a-ture of test medium (>2000 F) atomization and vaporization could occur that would not be detected.
The licensee stated that they would review their methods of inspection. This is an open item and will be reviewed at a
-
subsecuent inspection (77-12-03).
Additional review o' this test will be performed at a subse-quent inspection upon issuance of the Test Procedure Number TP 2C0/4, Reactor Coolant System Hydro Test.
7.
Test Procedure '!crification The inspector scriT'il atttas of licensee program for issuance of preoperational procedures that have been reviewed and approved and that the test obje. ti.es are consistent with test titles.
The licensee has completed the majority of required procedures.
Nine areas remain to be verified prior to completion of preoperational test procedure issuance.
(
i 80 256.
-
...
.
-
,.
-
-
'
.
~
8.
Plant Tour The inspector toured Auxiliary Building and Reactor Building with particular attention to the following areas:
Reactor Vessel and Pressure Vessel activities, Diesel Rooms, Radwaste areas and 4KV Bus areas.
The inspector did not identify any inadequacies.
.
.
<
80 357
.
4