ML19291B665
| ML19291B665 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/03/1977 |
| From: | Davis A, Fasano A, Ruhlman W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19291B661 | List: |
| References | |
| 50-289-77-03, 50-289-77-3, 50-320-77-05, 50-320-77-5, NUDOCS 7911110065 | |
| Download: ML19291B665 (20) | |
See also: IR 05000289/1977003
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IEst Form 12
( O 75) (Rev)
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U. S. NUCLFAR REGULATORY CCMMISSION
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0FFICE OF INSPECTION AND ENFORCDiEITI
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REGION I
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50-289
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IE Inspection Report No:
50-289/77-03 and 50-320/77-05
Docket No:
50-320
UPa-bo
Licensee:
Metropolitan Edison Company
License No:
CPPR-66
P. O. Box 542
Priority:
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t,
B-1
Reading, Pennsylvania
19603
Category:
Safeguards
Location:
Middletown, Pennsylvania (Three Mile Island)
Type of Licensee:
Ty')ofInspcetion:
Routine, Announced
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Dates of Inspection:
February 2-4, 1977
Dates of Previous Inspection:
February 1-3, 1977
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Aoet-C
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Reporting Inspector:
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A. N. Fasano, Repctor Inspector
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Accompanying Inspectors:
I/a/77
A. t. H
el
Reyctor inspector
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W. A
man,
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nspector
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Other Acce=panying Personnel:
None
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Reviewed By:
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A. B. Davis, Section Chief, Reactor Projects Section
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No. 1, Reactor Operations and Nuclear Supoort Branch
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791111oOGS
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SUMMARY OF FINDINGS
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Enforcement Action
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A.
Violations
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None.
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B.
Infractions
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None.
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C.
Deficiencies
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None.
Licensee Action on Previously Identified Enforcement Action
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Corrective actions taken in response to Region I Inspection Report
50-289/76-24 Item 76-24-18, were completed.
(Detail 10)
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Design Changes
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Not inspected.
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Unusual Occurrence
Reportable Occurrence 77-01/IP was reported to the inspector onsite.
During Surveillance testing both the Diesel Generators (DG) were found
to have a condition affecting the capability to start in a response to
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a loss of off site power.
The DG's would have started if receiving an
Engineered Safeguard Signal (ES).
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The failure resulted from the revolution cranking timer reaching its
limit before oil pressure limit switch (OPLS) reaching a required
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pressure to actuate. When the revolution cranking timer operates
before the OPLS actuates the DG trips. This DG trip is blocked on
an ES Signal.
The cause of the problem on the "B" DG was only the cranking timer
setting. The "A" DG also had a defective OPLS.
The licensee transmitted a written report on this occurrence.
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Other Significant Findings
A.
Current Findings
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Acceptable Areas
(These are items which were reviewed on a sampling basis and
findings did not involve any Items of Noncompliance, Deviations
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or Unresolved Items except where noted under Unresolved Items.)
a.
Operational Staffing.
(Detail 3)
b.
Operating Staff Training.
(Detail 4)
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c.
Plant Operation.
(Detail 5)
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d.
IE Bulletins.
(Detail 6)
e.
Containment Spray Chemical Addition Tank NaOH (TM1-1).
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(Detail 7)
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Containment Spray Chemical Addition Tank NaOH (TM1-2).
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(Detail 8)
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Nonroutine Event Reports.
(Detail 9)
h.
Corrective Actions for Previously Identified Enforcement
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Item.
(Detail 10)
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Diesel Generator Load Sequencing Survey.
(Detail 12)
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2.
Unresolved Items
a.
TM1-2
77-05-01 Revise FSAR to provide corrected information for
question 412.1/13.1.1.4 with respect to degrees
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held by personnel.
(Detail 3.c)
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77-05-02 Have individual T complete the required FSAR
training or document exception taken.
(Detail
4.c)
77-05-03 Define training programs, in writing, for
personnel in maintenance and I&C departments
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as required by GP 0007 for continuing retrain-
ing items.
(Detail 4.e)
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77-05-04 Procedural or Technical Specification temper-
ature limits for the Sodium Hydroxide tank
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solution is needed.
(Detail 8)
b.
_TM1-1
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77-G3-01 Replacement of BFD relays during the 1977 re-
fueling outage.
(Detail 6.d.(2))
77-03-02 Procedure change adding a definition for a
'naximum concentration limit of Sodium Hydroxide
to assure that the term nominal 20% is within a
range of 2%.
(Detail 7)
77-03-03 Inspection of bearings on AH-VIA,18, and IC to
be completed during the 1977 refueling outage.
77-03-04 Modification 569, with respect to Radiation
Monitor RM-A2, is scheduled to be completed during
the 1977 refueling outage.
(Detail' 9.c. (5))
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B.
Status of Previously Identified /0ther Items
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The following items have been resolved /cksed:
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76-24-1 Test performance on Relays.
(Detail 11)
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76-24-6 Maintenance instruction and training.
(Detail 11)
76-24-18 See Licensee Action on Previously Identified Enforcement
Action.
Management Interview
A.
Entrance Interview
An entrance interview was conducted at the TM1 site on February 2,
1977, with the Unit 1 Superintendent and the Supervisor of Operations.
During this meeting the inspector described the scope, estimated
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duration, personnel to be contacted and records to be reviewed as
part of the inspection.
B.
Exit Interview - TM1-2
An exit interview was conducted at the site on February 3,1977, at
the conclusion of the TM1-2 phase of the inspection.
The attendees
are marked with an asterisk as shown in. Detail 1, Persons Contacted.
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The following summarizes the items discussed:
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Operational Staffing.
(Detaii 3)
2.
Operating Staff Training.
(Detail 4)
C.
Exit Interview - TH1-1
An exit interview was conducted at the site on february 4, 1977, at
the conciusion of the inspection with the following Licensee attendees:
Mr. J. J. Colitz, TM1-1, Unit Superintendent
Mr. W. W. Cotter, Supervisor, QC
Mr. G. A. Kunder, Supervisor of Operations
Mr. J. P. O'Hanlon, Unit Superin'tendent - Technical Support
Mr. M. A. Shatto, Engineer Associate II, Nuclear
The following sumarizes the items' discussed:
1.
Piant Operations.
(Detail 5)
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2.
IE eu11etins and Circulars.
(Detati s)
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3.
Containment Spray Chemical Addition Tank NaOH.
(Detail 7
and 8)
4.
Nonroutine Event Reports.
(Detail 9)
5.
Diesel Generator Load Sequencing Survey.
(Detail 12)
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DETAILS
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Persons Contacted
General Public Utilities (GPU)
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Mr. J. R. Thorpe, Chairman - Three Mile Island Nuclear Station GORB
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Metropolitan Edison (Meted)
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Mr. S. H. Bailey, Jr., Mechanical Engineer II
Mr. R. W. Bensel, Electrical Engineer Unit 2
Ms. R. S. Brown, Technical Analyst III
- Mr. M. Bezilla, Engineer I
Mr. J. J. Colitz, TM1-1 Unit Superintendent
Mr. J. C. Fornicola, Quality Control Engineer
Mr. E. F. Gee, Quality Control Specialist (Receipt Inspector)
Mr. C. E. Hartman, TM1 Lead Electrical Engineer Unit 1
Mr. K. R. Hoyt, Control Room Operator
Mr. R. M. Klingaman, Manager-Generation Engineering
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Mr. M. S. xaudsen. Auxiliary Operator "A" nuclear
Mr. R. G. Kokstein, Quality Assurance Engineer II
Mr. G. A. Kunder, Supervisor of Operations Unit 1
Mr. B. W. Leary, Mechanical and Systems Engineer I
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Mr. C. F. Leonard, Mechanical Maintenance Foreman
- Mr. G. P. Miller, TM1-2 Unit Superintendent
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Mr. W. McGettrick, Instrument and Control Engineer
- Mr. M. A. Nelson, PORC Secretary Unit 2
Mr. W. E. Potts, Supervisor of Licensing
Mr. J. C. Powell, Quality Control Assistant
Mr. R. N. Prabhakar, Quality Assurance Section Head
Mr. G. Reed, Chemist Foreman
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Ms. K. M. Ritchey, Clerk Junior
Mr. M. Ross, Shift Supervisor Unit 1
- Mr. J. L. Seelinger, Unit 2 Superintendent-Technical Support
Mr. M. A. Shatto, Engineer Associate II, Nuclear
Mr. E. Sheets, Electrical Engineer
Mr. H. Shipman, Operations Engineer II
Mr. J. W. Sipe, Sr., Instrument Technician Nuclear
Mr. C. W. Smyth, Lead Unit 2 Licensing Engineer II
Mr. J. R. Stair, Licensing Engineer I
Mr. R. Summers, Engineer Nuclear II
- Mr. A. Tsaggaris, Assistant Director-Generation Training
Mr. R. F. Van Stry, Administrator-Nuclear Technical Training
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- Mr. R. W. Williams, PORC Chairman Unit 2
- Mr. R. W. Zechman, Group Supervisor-Technical Training
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jr }}9 Present at exit interview on February 3, 1977, TM1-2.
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i 6 2. Purpose and Scope of the Inspection This was an announced inspection which addressed a survey of TM1's Diesel Generator, D/G, Load Sequencing under various conditions. < The inspection also included a review of the following: I Operation staffing requirements for TM1-2. -- ! Training requirements for TM1-2 staff. -- ! Plant operation activities of TM1-1. - -- i IE Bulletin action follow-up by TM1-1. --
Sodium hydroxide concentration and temperature limits for -- TM1-1 & 2. Reportable occurrence follow-up action for TM1-1. -- This report, with respect to the D/G survey will be forwarded to {') NRR Headquarters for appropriate action. 3. Operat'ional Staffing (Unit 2 unless stated otherwise) . The licensee is committed (Technical Specification 6.3.1) to meet ANSI N18.1 requirements for qualification of personnel. The inspec- tor reviewed the qualification requirements of the following portions of the licensee's organization to verify that personnel were filling i the positions described in the FSAR Section 13, that personnel were l qualified to fill these positions as described in ANSI N18.1 or in the licensee's response to question 412.1/13.1.1.4. Results are summarized below. a. Operating Organization The inspector reviewed the qualifications for personnel filling the positions listed below to assure that they met the minimum qualification / experience requirements. Unit 2 Superintendent -- Supervisor of Operations -- Unit 2 Superintendent-Technical Support -- b 2 Radiochemistry Technicians -- 1532 320 , _ __ - _ _ . __ ._ _ ._ . _ ._
i b 7 .l All (15) operators presently being considered for Cold -- R0 Licenses All (6) operators presently being considered for Cold -- SR0 Licenses 2 Instrument and Control Technicians -- 2 Electricians -- j 3 Mechanical Maintenance Technicians -- i 3 Auxiliary Operators "A" -- Personnel in the following positions support both Unit 1 and Unit 2. Their qualifications had been previously verified as part of the Unit 1 inspection program. Supervisor of Maintenance -- a Shift Supervisors -- Nuclear Engineer ' -- 1 Instrument and Control Supervisor -- , Supervisor of Mechanical Maintenance --
j Supervisor of Electrical Maintenance -- Welding and Non-Destructive Test Personnel -- The inspector identified no discrepancies. . b. Quality Assurance / Quality Control Organizations The inspector reviewed the QA/QC organizations with respect to the requirements specified in the Quality Assurance Plan and the FSAR. The qualifications of personnel listed below were also reviewed. Manager of Quality Assurance -- Supervisor of Licensing -- Supervisor of Quality Control ( -- 1582 321 -- . .- . . .- - . ._ -
- . . _ . _ _ . . _ . _ _ . _ . . . _ _ . . ._ O 8 . . , 2 OA Auditors -- I 2 QC Technicians -- 2 QA Licensing Engineers -- The inspector identified no discrepancies. c. Technical Support Organizations The inspector reviewed resume's and a cross-reference listing prepared by the licensee to assure that GORB members were qualified in fields of expertise as required by ANSI N18.7. The inspector identified no discrepancies. The inspector reviewed the current assignment of personnel in engineering disciplines with respect to the licensee's staffing positions as stated in answer to Question 412.1/13.1.1.4 as given in Amendment 39 to the FSAR. The inspector found that the number of engineers / degrees met or exceeded the licensee's O statements with the following exceptions: Answer 2.d states that an individual holds 2 B.S. degrees, -- the individual currently filling that position has a degree in Mechanical Engineering; Answer 2.d(1) indicates that one individual has a Ph.D. the -- individual was a candidate for the Ph.D. degree prior to coming to this country, but the degree was never obtained. The licensee stated that these two incorrect entries would be revised in a subsequent amendment to the FSAR. Until this in- formation has been corrected, this item (77-05-01) is unresolved. 4. Operating Staff Training (Unit 2) The inspector verified that training commitments in the FSAR, Section 13.2 had been established and conducted commensurate with the time prior to licensing. Responsibilities for administration / evaluation - had been assigned in this area. . a. Program The programs as established covered the following areas: u i i i 1532 322 . . - - . .- - -_- - - -._ . . --
.-. - - .. .. . .. --. -. . . . - - . -. I O 9 . administrative controls; -- , radiological health and safety; -- controlled access and security; -- , ! i emergency plans and procedures; -- industrial safety; -- fire fighting; -- quality assurance program; -- and for female employees, instructions concerning prenatal -- radiation exposure. The inspector identified no discrepancies. b. On-The-Job Training O The FSAR commitments for on-the-job training had been establis.hed . and carried out for personnel in the following classifications:
control room operators; --
auxiliary operators; ' -- mechanical maintenance personnel; -- electrical maintenance personnel; -- technicians; -- QA/QC personnel; and { -- other members of the technical staff. -- The inspector identified no discrepancies, c. Records Review The inspector selected and reviewed records for at least two individuals in each of the classifications listed below: ' ( . . ) J 0 L. l . .. - .-. . -. . . . - .
. - - - - - - . - - - () i 10 t . reactor operator candidates (reviewed for all candidttes); -- . senior reactor operator candidates; -- , i maintenance-mechanical craftsmen; e -- I maintenance-electrical craftsmen; -- instrument and control technicians; -- QC personnel; j -- } radiochemistry / radiation protection technicians; - -- female employees; -- engineering staff personnel . -- The inspector found that one Cold License candidate, Individual T, had entered the training program later than the rest of the I p' candidates and had, therefore, not completed the same percentage of FSAR requirements. The licensee stated that this individual could complete the requirements prior to licensing examinations. In some cases, the individuals past experience may be comparable , ! to the training courses in the FSAR. The licensee will assure i that this individual: Completes the required training; has in- l complete FSAR training documented in his Cold License application with justification for exceptions; or, is not considered for a Cold License. The inspector stated that, until one or more of the above options have been completed, this item (77-05-02) is ! unresolved. d. Personnel Interviews Without attempting to determine that the individual was qualified to hold the current position, the inspector questioned the indi- , viduals listed below to assure: That the training, as documented, had been conducted; that the person interviewed understood the material presented and had an opportunity to have any questions answered; that the interviewees understood the NRC's function with respect to the licensee; that the individuals understood their rights for access to NRC personnel; and that for personnel involved in engineering, QA and/or QC functions, personnel felt that quality related problems which they identified were appro- priately handled. n U 1582 324 - - -. . _
.. . . .- ... - (.) 11 . . one mechanical engineer; -- one licensing engineer; --
one QA auditor; -- } one QC receipt inspector; -- I ! one QC engineer; -- ~! one female employee; -- one auxiliary operator; -- ! one Cold License candidate; -- one electrician; -- i one mechanical maintenance craftsman; and, -- {) one instrument and control technician. -- . The inspector identified no discrepancies or inconsistencies with the interview results and the licensee's training documenta- , tion. e. Retraining / Continuing Training , l l Generation Procedure 0007 requires each department to define retraining / continuing training programs. This procedure also i contains the caveat that: . . .Al though written for all Genera- " tion Division personnel, implementation of this procedure at Nuclear Power Plant Sites will be deferred to a later date..." The Procedure is dated July 20, 1976, for Revision 2. The licensee stated that, since initial (FSAR) training programs will assure that initial proficiency is achieved, the programs to define the continuing / retraining aspects of maintaining pro- ficiency would be written prior to issuance of the Operating License and subsequently implemented. Until these programs have been written for the mechanical, electrical and instrument and control departments on site, this item (77-05-03) is unresolved. ' ? 1532 325 .. . - - - - . - _
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a. Shift Logs and Operating Records The inspector reviewed the records listed below, held discus- . sions with plant staff members and inspected the control room j on February 4, 1977. (1) Shift Foreman's Log, January 12 to February 4,1977, Daily Check Sheet, February 4, 1977, and Control Room Operator Log January 29 to February 4,1977, were re- viewed to verify that: (a) log sheets are completed properly (b) documentation involving abnormal condition provide sufficient details to communicate equipment status; lock out status, correction and restoration; and, (c) log book reviews are being conducted by the staff. - ( .) ' (2) Jumper / Lifted Lead Log: All entries subsequent to - August, 1976 were reviewed. All entries were dated and j initialed. No discrepancies with Technical Specifications I were observed. i b. Observation of Activities in the Control Room ! The inspector made the following observations in the Control Room:
(1) Control Room strip charts were observed to be inking and j were legible. t l (2) Control Room Manning: The inspector observed that the operating shift was staffed in accordance with the re- ! l quirements of Technical Specification 6.2.2.a and 10 CFR 50.54(k). (3) The inspector discussed with the Control Room Operator the reasons for the selected lighted annunciators. The Control Room Operator was aware of the alarm in- dications and the reasons for the lighted state. 3 - 1582 326 . . - . -- - . . - _ . -. _.
-.- . -. . . - () 13 . . k j 6. IE Bulletins and Circulars ! a. Selected IE Bulletins and Circulars were reviewed to verify that: ' i j (1) information was forwarde'd to onsite management; (2) information discussed in the licenste's reply was sup- parted by facility records, or by visual examination of the facility; (3) Corrective action taken was effected as described; (4) the reply by the licensee was prompt and within the time period in the bulletin letter considering mail delays. b. The IE Bulletins reviewed were: (1) 76-02 Relay Coil Failures - GE Type HFA, HGA, HKA, HMA Relays and 76-03 Relay Malfunctions - GE Type STD Relays. (2) 76-05 Westinghouse BFD Relays. (3) 76-07 and Circular 76-01 Crane Hoist Control - Circuit Modi fications . c. The IE Circular reviewed was: 76-02 Relay Failures - Westinghouse BF(ac) and BFD(de) Relays. d. The inspector's findings were acceptable except for the Unre- solved Items delineated below.
(1) With respect to Bulletin 76-02 and 76-03 Work Request ' 14624, March 26, 1976, contained the survey results of . the inspection of spools. The spools were of the accept- ' able black type. The licensee has no STD relays in use on TM1-1. (2) With respect to Bulletin 76-05 and Circular 76-02, Work Request 14701 verified a drop out test and internal memo shows temperatures to be 800C. Also, Work Request 14606 documents a functional test of the BFD's. ( 1532 327 . . . -.. -- .- _. n . . - - - m ,, - . . . . . . - . - - -
_ __ _ _ _ i () 14 . . f There are 34 BFD's in the Diesel Generators. They will be replaced during the 1977 refueling outage. This is an Unresolved Item (77-03-01) pending the final replace- ment. , , I (3) With respect to Bulletin 76-07 and Circular 76-01, internal ' memorandum and correspondence dated September 8, 1976 and August 24, 1976, with the hoist manufacturers and the i electrical contactors manufacturers were reviewed. Work Request 16526 verifies the checking of the contactor. 7. Containment Spray Chemical Addition Tank NaOH (Unit 1) The following documents were reviewed: NRC Communication, October 22, 1976, Chemical Spray Chemical -- Addition Tank NaOH TM1-1 Technical Specification 3.3.1.3, Reactor Building Spray -- System and Reactor Building Emergency Cooling System Sodium Hydroxide Concentration, Form 1301-6.5-1, Revision 3, . -- August 13, 1976 Control Room Operator Log Sheet, sheet 1, item: Sodium Hydroxide -- Tank Level-LT-472 (Posted per 1301-6.5) and item: Sodium Hydrox- ide Tank Temperature-BS-7T (550 to 650F) Reactor Building Spray System, 1104-5, Revision 7, November 16, -- 1976
' The Technical Specification requires that the Sodium Hydroxide Tank shall contain not less than 16,000 pounds and not more than 17,000 pounds of NaOH. The Na0H will be stored at a nominal 20 weight per- cent solution. , Procedures reviewed specify temperature limitation of 500F minimum and 1200F maximum. Procedures also require chemical sampling quar- terly or after any change to the tank content. Determinations are made by procedure for tank volume (height) limits which fix the nominal concentration at 20 weight percent or above. The upper value, based on nine reviewed data sheet for 1976, was 20.8".. At this concentration and at temperatures of 500F, minimum, precipitation will not occur. s 1532 328 -___ . - -- - .. - -.. _ -.
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The level determinations, once calculated, are posted on the Control Room panel indicator. Both an upper and lower limit are posted. The reactor operator records the actual tank level and tank tempera- ture every shift. , To assure that the nominal concentration is within the soluable rangc, procedure 1104-5 will be amended to include a statement that specifies , a minimum tank volume (level) based on the maximum Technical Specificc- ! tion NaOH weight limit at the minimum temperature of 50 F and be with- 0 l in a defined nominal weight percent of no greater than 22*.'. This is Unresolved Item 77-03-02, and will be resolved pending the approval of the amended procedure. , t 8. Containment Spray Chemical Addition Tank NaOH (Unit 2) j The following documents were reviewed: ' NRC Communications, October 22, 1976, Chemical Spray Chemical -- Addition Tank NaOH fp TM1-2 Draft Technical Specification 3.6.2.2.a. -- 3 _ The Technical Specification specifies a minimum and a tentative max'- ' imum volume limit in gallons of solution with a minimum and a tenta- tive maximum concentration in ppm of Sodium Hydroxide. The Technical ' Specification does not specify a temperature boundary. Temperature ' i limits, either in the Technical Specification, TS, or in procedure l would assure against precipitation. Procedures have not been written l to date on the Sodium Hydroxide tank. This is Unresolved Item 77-05-04 and will be resolved pending a TS addition and/or coverage in procedure ! as is done in Unit 1. ' 9. Nonroutine Event Reports (Unit 1) a. Selected Reportable Occurrences were reviewed to verify that: (1) The cause was identified and that details were clearly re- ported to the NRC and facility management; (2) Corrective action described in the licensee's report was taken to prevent recurrence; (3) Each event was reviewed and evaluated as required by the Technical Specification; and ( i (4) Safety limits, limiting safety system settings were not exceeded and corrective action was taken when a Limiting Condition for operation was identified. 1582 329
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l'; ! 16 i . . ! l This review included physical observations of affected equip- i ment / components and implementation of corrective actions where appropriate, discussions with members of the plant staff and inspection of PORC meeting minutes, internal site memos and ' the documenting of requirements of TS 6.6, Shift Foreman's Log, Work Requests (WR's), Surveillance Test Records and proce- , dure changes.
b. The Reportable Occurrences reviewed were: I ' (1) ER 76-36/1T Plant Water Discharge Disolved Solids Concen- tration in Excess of Limits Defined by the Environmental Technical Specifications. (2) ER 76-37/1T Overlap Between Control Rod Group Six and Seven Exceeding the Allowable 30% Limit. (3) ER 76-38/3L Failure of the High Reactor Coolant Temperature Trip Bistable to Trip During Test. O (4) ER 76-44/3L Reactor Building Containment Isolation Valve AH-V10 Failed to Fully Close. (5) ER 76-45/3L Radiation Monitor RM-A2 Removed from Service for Repairs. (6) ER 76-46/1T Concentration of Boric Acid in the Borated Water Storage Tank Less than Minimum Limit. (7) ER 76-47/1T Amount of NaOH in the NaOH Tank Less than l Minimum Limit. l (8) ER 76-49/3L Failure to Test Decay Heat Removal Pump "A" Before Recirculation of the Borated Water Storage Tank ! with Decay Heat Removal Pump "B".
c. The inspector's findings were acceptable except for the Unre- solved Items delineated below. (1) With respect to ER 76-36/1T, a mechanical stop has been installed and was visually verified. s 1532 330 - - -- - - - - . _ . .- .
. . . I (\\ 17 . . (2) With respect to ER 76-37/1T, Response to Alarm G-2-2, Revision 2, change was reviewed. The change requires an increase in communication and the use of the Auxiliary Power supply for a similar event. The computer summary reviewed indicated that this overlap condition was over a time period less than one hour.
(3) With respect to ER 76-38, Work Request 17478, which con- tained the required instruction for corrective action, was reviewed. The histable contacts were cleaned and Channels A, B and D ere checked to assure protection (Surveillance procedure 1303.4.1). (4) With respect to ER 76-44/3L, the Work Request 18001, December 6,1976, verified corrective actions taken on the valve. The valve was tested, reference surveillance test 1303, December 26, 1976. A lubrication schedule has been established, Intermediate Building, Machine Shop and Control Building Equipment Tube. (] The inspection of the bearing opposite the operator on AH-VIA,18 and 1C remains to be completed. This is an Un- resolved Item, (76-03-03). The licensee plans to complete this inspectien during the 1977 refueling outage. (5) With respect to ER 76-45/3L, modification 569 remains to be completed. This is Unresolved Item 76-03-04 and is scheduled to be completed during the 1977 refueling outage. (6) With respect to ER 76-46/1T, discussions with the licensee indicate that instructions on sampling have been given to the chemist. (7) With respect to ER 76-47/1T, Surveillance Procedure 1301-6.5 has been changed, Revision 4, to minimize incorrect reading of the graphs. (8) With respect to ER 76-49/3L, procedure 1301-4.4, Borated Water Storage Tank Weekly Surveillance, Revision 3, January 3,1977, has been changed to assure better personnel communication and procedural action. t iL2 331 -.. _ . . . . . . .
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18 ' . . 10. Corrective Action for a Previously Identified Enforcement Item ' Unit 1 Reference: NRC Inspection Report 50-289/76-24, NRC letter dated , November 5, 1976 and. Met Ed letter dated November 29, 1976. The inspector reviewed the licensee's corrective action which in- ' cluded the licensee's completed written list, dated January 7,1977, i which appoints / designates alternate members for each permanent member i of the GORB. This item is considered closed. 11. Status of Previously Identifled Items (Unit 1) { 76-24-1 Test Performance on Relays , l lack of relays meeting monthly performance test requirements had been identified by the licensee in ER 76-16/3L and ER 76-5/1T. (Inspection Report 50-289/76-24) During this inspection the inspector audited Work Request 17434 with (",) attached test procedure and data sheets. This work request required Clark PMAC Convertible Pole Relays in stock to be tested in accordance with the test procedure attached to Work Request 17454. The inspector examined the test data taken during the testing of the relays and con- curred that the data met the test procedure requirements. Each relay received a visual examination for damage and a verification that the spring tail was seated correctly in the relay. Data was signed, dated and approved by the reviewing engineer. This item is resolved. 76-24-6 Maintenance Instructions and Training
Failure of GE 600 volt breaker to trip on a reactor protection system test signal had been identified by the licensee in ER 76-10/3L. ' (Inspection Report 50-289/76-24) l During this inspection the inspector audited the change to Preventive Maintenance Procedure E-36, Revision 1, dated December 30, 1976, and the attached data sheet. Paragraph 6.4 of procedure E-36 defines the type of lubricant required. In addition to the above, a training course has been contracted between the licensee and the General Electric Cenpany. This course is scheduled for the period of February 14-18, 1977. The course is titled Electrical Maintenance, and is being provided for the plant electrical maintenance personnel and selected engineers. Reference licensee purchase request No. 100-4731. This item is resolved. 1532 D2 __ ._ -_ _. _
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12. Diesel Generator Load Sequencing Survey (Unit 1) Reference: NRC Region I letter to licensee dated January 14, 1977. The licensee was informed by reference (1) of a planned inspection of the facility to determine the diesel generator load sequencing in event of loss of offsite power following a LOCA and subsequent 4 , to safety injection system reset. The inspection was performed in ! conjunction with this routine announced facility inspection. The diesel generator load sequencing was reviewed to determine: , Safety Injection System (SIS) reset features. -- l SIS procedural requirements and basis for procedural action. -- Diesel Generator (D/G) emergency starting signals. -- i D/G load sequencing conditions. -- Loads sequenced for continued operation of D/G's. -- , . _ . ' ~') ( D/G testing performed. -- . l D/G load sequencing after SIS reset. -- 4 The review included observation of installed equipment and controls, a review of applicable drawings and procedures and discussions with , j licensee personnel, i Information related to the inspection of D/G load sequencing is being I ' sent to NRC: NRR for review. , s 1552 333 - - . _ _ . . - -.-_._. - . __ _. -. .. }}