IR 05000440/1985073
| ML20134B122 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 10/31/1985 |
| From: | Scheibelhut C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20134B115 | List: |
| References | |
| 50-440-85-73, 50-441-85-24, NUDOCS 8511110284 | |
| Download: ML20134B122 (11) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No.
50-440/85073 (DRP); 50-441/85024 (DRP)
Docket No.
50-440; 50-441 License No.
CPPR-148; CPPR-149 Licensee: Cleveland Electric Illuminating Company Post Of fice Box 5000 Cleveland, OH 44101 Facility Name: Perry Nuclear Power Plant, Units 1 and 2 Inspection at: Perry Site, Perry, OH Inspection Conducted: Octobqr 7 11 and October 14-18, 1985 h
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Inspector:
C.'s. Sche)belhut
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I Date Approved by:
R. C. Knop, Chief Reactor Projects, Section 1A Date Inspection Summary
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Inspection on October 7-11 and October 14-18, 1985 (Reports No. 50-440/85073 (DRP); 50-441/85024 (DRP))
Areas Inspected: Routine safety inspection by a Regional Inspector of licen-see actions on previous inspection findings, 10 CFR 50.55(e) items, and evalu-ation of licensee action with regard to IE Circulars, confirmatory items called for in the Safety Evaluation Report, and allegations. The inspection involved a total of 72 inspector-hours onsite by one NRC inspector and includes 0 inspector-hours during off-shifts.
Results: No violations, deviations, or safety significant issues were identi-fied.
8511110284 85
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Details
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1.
Persons Contacted L
Cleveland Electric Illuminating Company C. M. Shuster, Manager,. Nuclear Quality Assurance Department (NQAD)
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J..J. Waldron, Manager, Perry. Plant Technical Department (PPTD)
S. F. Kensicki, Technical Superintendent, PPTD
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R._L. Vondrasek, General. Supervising Engineer, Nuclear Engineering
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G. Chasko, Surveillance Engineer, PPTD l
B. B.-Liddell,; Operations-Engineer, PPTD R. L. - Luse, Support Services Engineer, PPTD
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N. ' J. Lehman, Staff Analyst, PPTD
,l R. ' A. Newkirk, Senior Staff Engineer, NED T. G. Swansiger,. Supervisor, NQAD.
I F. EH. - Sondgeroth, Senior. Engineer, NED The above' listed personne1' attended the exit. interview on October 18,
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1985.
The inspector also' interviewed other licensee and contractor
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l personnel during the course of the inspection.
l 2.-
Licensee Actions on Previously Identified Items (92701, 92702)
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a.
(Closed) Unresolved Item (440/85010-04 (DRP)):
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Response Instruction Discrepancies".
During a review of the Standby l
Liquid Control System (SLCS) preoperational test, the inspector j
found four instances of Alarm Response Instructions (ARI)
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identifying incorrect annunciator locations. Also, one annunciator
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had no ARI. Additionally, there was inconsistency between the FSAR, Technical Specifications, preoperational-test procedures and an ARI
with respect' to the high and low storage tank level setpoints.
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The four annunciators incorrectly located in the ARIs were moved as
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a result of the Detailed Control Room Design Review (DCRDR).
The
i annunciator.not covered by an ARI was added by the DCRDR.
There was
an inconsistency among the various documents in the storage tank
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level setpoints.
j The licensee is in the process of rewriting all ARIs written in the l
system specific format such as ARI-C41 covering the SLCS. These
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l ARIs are being rewritten into a panel based format such as ARI-H13-
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P601-18 and H13-P601-19 covering the SLCS and other systems.
This
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l 1s being done to place the ARIs in a format more useful in the
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i control room.
Special Project Plan 0501, " Operations Manual Verifi-
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cation", was initiated to provide additional assurance that plant I
operation commitments are identified-and incorporated into the
. operations manual.
The plan also' requires review of all operations
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manual instructions for consistency'with the as-built condition of-
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the plant. The inconsistencies in the SLCS storage tank' low level l
and high level setpoints have'been resolved.
The-FSAR will continue to not show the values.
The Technical' Specification values have-been' incorporated into the pertinent ARIs and preoperational test.
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'These setpoint changes were made,in accordance with Plant Adminis-
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trative Procedures (PAP)-1403, " Control of Setpoints", and received j
the. required review.
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.The inspector reviewed the approved ARIs-H13-P601-18 and H13-P601-19
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j and inspected the panels and found them in agreement. The inspector also reviewed the Technical Specifications for SLCS high and low j
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i, level setpoints and found agreement in the.ARIs and amended pre-
operation test procedure, TP IC41-P-001, for the SLCS and found j..._
agreement. The inspector also reviewed Special Project Plan 0501
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and PPA-1403 and concluded that concerns of this nature will be 7.-
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satisfactorily reviewed and resolved. This item.is closed.
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(Closed) Open Item-(440/85033-15 (DRP)):
_" Review of 8 Routine
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j Battery Surveillance Instructions". As part of a regional request, the inspector reviewed the licensee's program for maintenance and
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testing of_the plant batteries for conformance to the requirements
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of Regulatory Guide 1.129, Rev.1, " Maintenance, Testing and Re-placement of Large Lead Storage Batteries for Nuclear Power Plants",
and IEEE-450, " Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for. Generating Stations and Substations". -The inspector found that the program conformed to the requirements and recommendations of the Regulatory Guide and IEEE Standard. However, Plant Maintenance Instruction-(PMI)-0024 contained all of the inspection requirements regardless of their periodicity. The inspector was concerned that this wo'uld cause confusion when implementing the instruction.-
The' licensee wrote three PMIs (-0034, -0035, and -0036) to cover.the weekly, quarterly, and annual-non-class 1E station batteries.
Also written were Surveillance Instructions (SVIs) R42-T502, Rev. 1,
" Weekly 125V Battery Voltage'and. Category A Limits Check", -R42-T5204, "125V Battery Category B Limits, Terminal Corrosion and Electrolyte Temperature Check" '(a quarterly check),- and -R42-T5207,
" Battery Racks / Cell Plates, Terminal Corrosion and Connection
. Resistance Check" (an 18-month check). The SVIs cover the Class IE station batteries. To cover water additions and equalizing charges to all batteries,. Generic Electrical Instructions (CEIs)-039 "Exide f
Battery Equalizing Charge", and -090, "CDD Battery Equalizing Charge", were written.
The inspector reviewed the above eight instructions, the Regulatory Guide and the IEEE standard and found that'the instructions ade-quately covered the requirements and'would not cause confusion when implemented. This item is closed.
(. Closed) Unresolved : Item (440/85033-20 (DRP)):
"VLI-R44-1,'Rev. 0, c..
Discrepancies".
During a review of Valve Lineup Instructions
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In one instance, the
.P&ID indication was open while the VLI indication was closed.
In other instances the P&ID indication was locked open while the VLI indication was open.
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In the first instance, the P& ids are generally drawn to show a system in operation, while the VLIs are written to show a " plant secured" status which is a benchmark status for writing operating instructions.' Therefore,. discrepancies between the two may be expected and are normal.
In the second instance however, commit-ments 'in the FSAR require certain valves to be locked open or closed and these commitments must be reflected in the P& ids and VLIs.
The licensee revised PAP-0503, " Preparation of Valve Lineup In-structions", to include the requirement'of showing valves locked open or closed if called for in the FSAR or other licensing commit-lments. A review was made of the FSAR and the other licensing com-mitments to identify all valves that are required to be locked.
.This' review has been completed.
Engineering. Change Notices (ECNs)
or Design. Change Packages (DCPs) have been written and approved to
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change the P& ids.'
Most of these have been completed and the others are in progress. Temporary Change Notices (TCNs) have been written to change the affected VLIs and are in effect.
-The inspector. reviewed the results of FSAR and commitments review, the ECNs and DCPs written, the revised PAP, and the TCNs written to change existing VLIs. The review showed that the locked valve
- commitments made in the FSAR and other licensee commitments are or will be reflected'in,the P& ids and VLIs. The particular VLI that
.the inspector examined previously. had been corrected. The revised PAP also permits the operating department to require locking valves that are not required to be locked by the FSAR and P& ids. These valves include cross connections between systems, isolation between portions of systems released for unit one operation and incomplete-portions of the remaining system, those related to Technical Speci-fications that would reduce man-hours expended on surveillance requirements, etc.
Thus, VLIs can'contain locked valve indications not shown on the P& ids. This situation is acceptable. The in-spector also determined that the bulk of the revised P& ids have been-included in hsendment 19 to the FSAR.
This item is closed.
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(Closed) Violation (440/85046-02-(DRP)):. " Untimely distribution and training for a temporary change *to PAP-1402 and procedural weak-nesses for controlling those activities". During a tour of the facility, the inspector noted that Temporary Change Notice (TCN)-005 for PAP-1402, " Control of Lif ted Leads, Jumpers, Temporary Electrical' Devices and Mechanical Foreign Items", was being entered s
into the control room operations manual seven days after its effective date.
Further inspection revealed that the effective date was the same as the approval date and no special arrangements were made for distribution of the procedure to the appropriate locations or training to the new procedure by'the involved personnel.
The licensee reviewed the implementation of PAP-1402 between its effective date and the date of entry into the control room' opera-tions manual. Although'several temporary. alterations were installed and removed during this period, the concurrences required by the TCN were obtained'using previously approved methods. The following corrective actions were taken
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I PAP-0502, " Preparation, Review, Approval, Revision and Cancel-e:
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lation of Administrative Procedures", has been changed to
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require that the date when a procedure or temporary change
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becomes effective shall permit sufficient time for training and i
controlled distribution.
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e PAP-0211, " Procedure and Instruction Training", has been
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changed to require training of appropriate personnel when a
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temporary change to a Plant Administrative Procedure is issued.
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e Administrative personnel involved in.the processing of pro-
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cedures and any subsequent temporary changes were reinstructed s
in the requirements for expeditious. processing of these docu-
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ments to controlled copy holders within required time limits.
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j Training of personnel affected by TCN-005 to PAP-1402 was
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accomplished.
t The inspector reviewed the revised PAPS-0502 and -0211 and found
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'that the required changes had been made. The inspector visited the training section and reviewed the records of training of personnel j
to-the requirements _of recent TCNs to administrative procedures.
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l The record of training of personnel to the requirements of TCN-005 to PAP-1402 was also reviewed.
The reviews showed that timely
training of personnel to the new requirements of TCNs to admin-
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istrative procedures is taking place, and sufficient time is allowed
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allows distribution of a TCN before its effective date.
This item I
is closed.
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e.
(Closed) Open Item (440/85066-01 -(DRP)): - Format Inconsistency in
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Approved SVIs".
The inspector found inconsistencies in the format L
of Surveillance Instructions (SVIs) written in accordance with two
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different revisions of Technical Administrative Procedure (TAP)-
j 0503, " Preparation of Technical Specification Surveillance j
Instructions". The earlier revision (3) did not indicate that
i quality records were generated as a result of performing the SVI.
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The later revision (4) had'the required records capture statement in l
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the format but did not indicate that'the data package cover sheet
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j was a quality record.
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The licensee issued TCN-001 to TAP-0503 to list by name all the r
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. quality records expected to be generated by performing the SVI.
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i licensee also indicated that any_ SVI run to fulfill a license re-j quirement.would be revised-or have a TCN to conform to the format
' indicated in TAP-0503, Rev. 4 and TCN-001.
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i The inspector reviewed TCN-001 to TAP-0503 and found it satis-factory. Since any-SV1 must conform to the latest version of TAP-l 0503 before use (either by revision or TCN), the inspector has no further concerns in this area. The item is closed.
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(Closed). Violation (441/84006-01):
" Material false statement con-
carning the use of herbicides to control vegetation along i
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transmission lines".
The inspector reviewed pertinent documentation concerning this violation including the Director's Decision under 10
~CFR 2.206 (DD-83-17), the applicant's response to the Notice of Violation dated April 25,_1984, and the NRC acknowledgement letter to the applicant dated' December 12, 1984.
The incomplete statement has been. corrected.
The NRC has concluded that the applicant's initial false statement and its failure to correct the staff's use of the statement in the Final Environmental Statement, did_not have significant regulatory
. impact nor appear to have been intentional.
This item is considered closed.
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(Closed) Open Lnspection Item (441/84025-02):
" Management control
of responses to inspection findings".
In. response to' an open-inspection item regarding the: test program,'the applicant revised a procedure which was subsequently changed deleting the programmatic requirements that-resolved the original concern.
To prevent recurrence of this type of breakdown, the applicant realigned the-test program organization placing'scre supervisory emphasis on,
. responsiveness to inspection findings and control over the process-ing of test section administrative procedure revisions. These actions appear to have been adequate due to the lack of recurrence of this type'of ites. This item is considered closed.
~ No violations or deviations were identified.
3.
Safety Evaluation Report Follow-up Inspection -Items (92701)
The Office of Nuclear Reactor Regulation (NRR) has requested that Region III inspectors confirm that the licensee has acceptably implemented certain Three Mile-Island (TMI) action items and confirmatory issues as described 'in the Safety Evaluation Report.(SER) for Perry, Unit 1 (NUREG-0887 with Supplements 1 through 6).
In Inspection Reports 50-440/85022, 50-441/85012, _ and 50-440/85033, these items were listed as Open Items and entered into the Region'III tracking system for future inspection.
The items reported below are the results of the inspection of certain of the items.
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(Closed) SER Open Item.(440/85022-01 (DRP)):
"THI Item I.A.1.1; a.
Verify that the licensee has implemented the on-shift technical advisor.- (S ER 13.1. 2. 4 - and ' 13. 5.1. 2)".
The licensee has imple-mented the requirement;for having a Shift _ Technical Advisor (STA) as t
. part of every operating shif t as follows:
Table 6.2.2-1, " Minimum Shif t Crew Composition", of the Perry e
Plant Technical Specifications indicates that an STA is re-
. quired during conditions 1, 2, and 3.
. Technical Administrative Procedure -(TAP)-0101, " Duties of the e
Shift Technical Advisor",' delineates the duties of the STA.
Training Manual (TM)-7.3, '" Departmental Training - Technical
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Section", delineates the training required for an STA.
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The ~ inspector reviewed TMI Item I. A.1.1, SER Sections 13.1.2.4 and 13.5.1.2, Technical Specifications, Table 6.2.2-1, TAP-0101, and TM-7.3.
The review showed agreement between the requirements of the
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.the TAP and TM.
The inspector also reviewed the STA training rec-
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ords and.found that the training required in-TM-7.3 for STAS has been completed for nine individuals. Of the nine, three are also licensed.SR0s. ~ Based on the above evidence, this item is closed.
b.
"TMI Item I.G.1; Determine that additional training is given during low power test-j ing.
(SER 14.2)."
The licensee wrote TM-D1.5, "Preoperational and Startup Test Train-
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- ing Program" to implement the requirements of TMI Item I.G. I. -
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The inspector reviewed TMI Item I.G.1 and TM-DI.5 and found that the
TM implements the requirements of the TMI item. The inspector also reviewed training records generated under TM-D1.5 and found that the training program is in progress.
This item is closed.
c.
-(Closed) SER Open Item (440/85022-18 (DRP)):
"TMI Items II.D.1 and II.K.3.16; Verify that testing of relief and safety valves has been completed. -(SER 3.9.3.2.1, 5.2.3, and 5.2.4)."
In SER Section
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3.9.3.2.1, it was concluded that the licensee had committed to the requirements of TMI Item II.K.3.16 to the extent practicable at this time. TMI Item II.D.1 requires testing of the reactor relief and safety valves under expected operating conditions for design basis transients and accidents.
General Electric Company (GE) supplied the reactor safety and relief valves for the Perry Plant. GE also supplied a certification test-
-i ing plan and-procedure (511.1216) and a product quality certifica-tion for each valve that indicated that the valve was tested in accordance with the plan.
The inspector reviewed the testing plan and procedure and the re-
quirements of Item II.D.1 and concludes that the valves were ade-quately tested to comply with the TMI item. This item'is closed.
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(Closed) SER Open Item (440/85022-23 (DRP)):
"TMI Items. II.F.1. 4,
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II.F.1.5, and II.F.1.6; Verify that instruments have been installed to monitor containment pressure, water level, and hydrogen.
(SER and SSER2 7.5.2. 5)".
On-April;23-25, 1985 certain members of the.
' Instrumentation and Control Systems Branch of the-Division of.
Nuclear Reactor Regulation, NRC, made a Perry site visit to verify certain aspects of the plant instrumentation and control system.-
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The group issued a trip report : documenting their findings. The report was transmitted to the licensee bygletter (B. J. -Youngblood
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to M. R. Edelman) dated May :31,1985.
Section h of the report details the review of containment pressure, water level, and
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hydrogen concentration instrumentation required by TMI Action Plan l
Items II.F.1. (4), (5), and (6).. The conclusion was that the instru-
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mentation adequately fulfilled.the requirements of'the TMI items.
Based on'the above verification,'this item is closed.
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'(Closed) SER Open Item (440/85022-24 (DRP)):
"TMI II.F.2; Verify
.that instrumentation for detecting inadequate core cooling have been
.SER, SSER3, and SSER5 4.4.7)".
In paragraph j of the (
installed.
trip report referenced in paragraph d, above, the staff reviewed the instrumentation pertinent to Item II.F.2.
They concluded that it was adequate and no concerns were identified.
Based on the above verification,-this item is closed.
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-(Closed) SER Open Item 440/85022-25 (DRP)):
"TMI Item II.F.3;
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Verify that instrumentation for monitoring accident conditions has
'been installed. -(SER,_SSERS, SSER6'7.5.2.2)".
In a letter from H. L. Thompson, Director, Division of Licensing, Office of Nuclear Reactor Regulation to C. E. Norelius, Director-Division of Reactor
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Projects, Region III,-dated October 10, 1985, Mr. Thompson withdrew
.his request for Region III verification of TMI Action Plan Item II.F.3. - Accordingly, this item?is closed.
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(Closed) SER Open Item (440/85022-33 (DRP)):
"TMI Item II.K.3.21; Determine that the. testing of the capabilities of the HPCS and LPCI systems is in accordance with TMI Action Plan Item II.K.3.21.
(SER 7.3.2.1)".
The TMI-item noted that HPCS and LPCI systems flow could be manually terminated by an operator.
Therefore, it required an automatic restart of these systems on loss of water level if an initiation signal were still present. The BWR Owners Group took,a position that the requirement was unnecessary for a number of reasons.
In SER Section 7.3.2.1, the staff supported the reasoning and concluded that the issue was resolved without the requirement for automatic restart of the HPCS and LPCI systems. Therefore, no verification is required and the item is closed.
h.
(Closed) SER Open. Item'(440/85022-37 (DRP)):
"TMI Item III.D.3.4; Determine that equipment to ensure control room habitability has'
been provided. ' (SEE 6.4)".
In SER Section 6.4 the staff found that the control room design. tisfied the requirements of TMI ltem III.D.3.4 and was acceptable.
Inspection Report 50-440/85017
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i details the witnessing of preoperation test TPOM25/26-F001, " Control
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Room Heating, Ventilation, and' Air Conditioning (HVAC)-and Eeergency J.
Recirculation System", by a Region III inspector. The successful j
conclusion of this test verified that the design was valid and the
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equipment satisfactory for operation. This item-is closed.
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No violations or devf.ations were identified.
' 4.
Licensee Actions on 10 CFR 50.55(e) Items.(92700)
a.
(Closed) 10 CFR 50.55(e) Report (440/81006-EE (DAR 56)):
"Nonsafety j-sensing lines on safety-related receiver tanks".
The design of the-division one and.two diesel generator air starting. system has two i
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compressed air receiver tanks and starting air compressors per
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diesel generator.
Each receiver tank was equipped with an air
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I sensing line and-pressure switch which automatically started its
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corresponding air compressor on low pressure.' 'The sensing line had a manually operated isolation valve at the tank. The tank and isolation valve were designed to seismic category I criteria. The
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sensing line and pressure switch were not designed to seismic cate-gory 1 criteria.- Therefore, during a seismic event, the line and/or
pressure switch could be assumed to fail and the receiver tank p
depressurize, thereby preventing the diesel generator from starting.
The licensee abandoned the pressure switch, sensing lines and valves
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and replaced them with blind flanges on the receiver tanks thereby eliminating the hazard. To start and stop the nonsafety-related air
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compressors the licensee utilized existing pressure transducers that l
sense the pressure in the right and left starting air manifold of
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the diesels. While this system is not safety related, it is t
j designed to seismic category I criteria and would not be assumed to
- fail during a seismic event. During preoperational testing of the y
diesel generator sets, the system performed satisfactorily.
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i The' inspector examined the equipment in the field and concurs that
'the hazard has been removed and the problem resolved. Since the
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changes have been made on the unit one diesels. only, this item is
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closed for unit one.
b.
(Closed) 10 CFR 50.55(e) Report (440/85010-EE (DAR 232))s
"Part 21 from Brown Boveri dated March 19. 1985, concerning 480 volt circuit j
breaker that may have damaged control-wire insulation".
The Brown j
Boveri Company (BBC) notified the NRC and the licensee of a j
potential deficiency with some BBC K line circuit breakers based on
experience at another nuclear plant. When the breakers were racked j-out to the full disconnect position with the compartment door
. closed, the top edge of a dust shield could damage the insulation on
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j auxiliary switch control wires.
BBC also submitted instructions'for l
repairing any damaged control wire insulation and adding a sponge
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rubber strip to the top back of the dust shield to preclude future damage to insulation.
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i The licensee submitted a 10 CFR 50.55(e) report to the NRC and wrote Nonconformance Report (NR) NDS 118 to document the potential-
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deficiency and provide a disposition. Under the NR, 36 Work Author-izations (WAs) were written to identify the. breakers that may be i
affected, inspect the individual breakers for insulation damage, repair damage found, and add'the sponge rubber strip to the dust
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shield. Quality control wrote -separate inspection reports to
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. document the inspection and work performed under the WAs. - A total
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of 96 BBC breakers, including two in the warehouse, were inspected
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for damaged insulation and installation of the foam rubber strip.
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No instance of damaged insulation was found. The foam rubber strips
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-were installed in all of the breakers inspected.
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The inspector reviewed the NR and associated WAs and QC inspection reports. The review showed that all potentially deficient breakers swere inspected for insulation damage and had a foam rubber strip
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l added in accordance with the BBC instructions.- The inspector also L
I examined five of the breakers, chosen at random, and found no insul-
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ation damage and the installed foam rubber strip. Since no.
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inspections or work were done on unit two breakers, this. item is
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closed for unit one only.
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c.
(Closed) 10 CFR 50.55(e) Report (441/79007-EE) (DAR 15):
" Natural gas pipeline break analysis".
This report concerns the possibility of a potential hazard imposed on the plant due to an accidental rupture of the 20" (diameter) natural gas (99% methane) pipeline that traverses the site.
The applicant's final report dated January 30, 1930, stated that the results of an analysis performed by NUS Corporation indicated that accider:s involving the release of natural gas from existing pipelines do not pose a hazard to the plant, as the concentration of the natural gas at all plant air intakes would be well below the flammable limit.
This item is considered closed.
No violation or deviations were identified.
5.
Evaluation of Licensee Action with Regard to IE Circulars (92717)
For the IE Circular listed below, the inspector verified that the Circular was received by the licensee management, that a review for applicability was performed, and if the Circular was applicable to the facility, appropriate corrective actions were taken or scheduled to be taken.
(Closed) IE Circular 80-04 (440/80004-CC, 441/80004-CC):
" Securing of Threaded Locking Devices on Safety-Related Equipment". Several licensee event reports were submitted to the NRC addressing the inoperability of safety-related equipment caused by loosened threaded locking devices.
.IE Circular 80-04 was issued in response to these events and listed the events.
It was recommended that the events be reviewed for applicability to the facility and that installation and maintenance procedures for safety-related equipment be reviewed to be sure the securing of locking devices is adequately covered.
The licensee reviewed the specific events in the Circular and found that they were not applicable to the Perry Plant. A review of the con-tractors' installation procedures was made.
Three procedures were found that were revised to include cautions on the securing of locking devices. The licensee's Nuclear Test Section (NTS) reviewed their pro-cedures and had to revise two procedures to address the locking devices. The licensee's maintenance section review of their procedures showed that three had to be revised to address locking devices.
The inspector reviewed the following revised contractor and licensee procedures:
L. K. Comstock and Company, Inc. procedure 4.3.1, " Cable Tray and Conduit Installation" Pullman Power Products Co. procedure JS-1X-55, " Maintenance, Repair,
Rework, Dicassembly and Reassembly of All Types of Valves"
Pullman Power Products Co. procedure 1X-55, " Disassembly and
Reassembly of Valves"
..
NTS Procedure GEN-E-003, " Motor Operated Valve Test" NTS Procedure TWP-M-032, " Disconnection of Air Operator Vortex
Maintenance Procedure adI-004, " General Maintenance Checks"
Maintenance Procedure MAP-0501, " Preparation and Formatting of Maintenance Instructions" Maintenance Procedure GEI-0014, "Limitorque Limit / Torque Switch
Adjustment" The review showed that in all cases, the revised procedures adequately addressed the proper installation of locking devices for threaded fasteners.
This item is closed.
No violations or deviations were identified.
6.
Licensee Actions on Allegations (99014)
Allegation (RIII-85-A-0138):
" Allegation concerning diesel generator control circuit design deficiencies".
This allegation was closed in Inspection Report 50-440/85066 because the licensee had corrected the deficiencies by modifying the control circuit design and changing the wiring to meet the new design.
The licensee subsequently informed the inspector that the required wiring changes have not been completed.
The inspector still considers the allegation closed for unit one because of the control circuit design changes that have been approved for unit one. However, completion of the wiring changes is considered an open item (440/85073-01) subject to further inspection when they are com-pleted.
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7.
Open Items Open items are matters which have been discus' sed with the licensee, which will be reviewed further by the inspector, and which will involve some action on the part of the NRC or licensee or both. An open iter dis-closed during the inspection is discussed in paragraph 6.
8.
Exit Interview (30703)
The inspector met with the resident inspector and licensee representa-tives (denoted in paragraph 1) at the conclusion of the inspection on October 18, 1985.
The resident inspector summarized the scope and find-ings of the inspection.
The licensee acknowledged the inspector's find-ings. The licensee did not indicate that any of the information disclosed during the inspection could be considered proprietary in nature.
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