IR 05000289/1978012
| ML19210B577 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/27/1978 |
| From: | Conte R, Keimig R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19210B565 | List: |
| References | |
| 50-289-78-12, 50-320-78-22, NUDOCS 7911110018 | |
| Download: ML19210B577 (11) | |
Text
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NUCLEAR REGULATORY COMMISS.vN OFFICE OF INSPECTION AND ENFORCEMENT Region I
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50-239/78-12 D*
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.ecor: Nc. 50-320/78-22 6E3
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a 50-2S9 Cocke: No. 50-320 CFR-50 C
License No. DPR-73 Priority Category B2
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Licensee:
Metrocolitan Edison Comcany
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P. O. Box 542
Readina. Pennsylvania 19603
/acility Name:
Three Mile Island Nuclear Station, Units 1 and 2 Inspection at:
Middletown, Pennsylvania Inspection conducted:
May 30 - June 2, 1978 Inspectors:
WbbkP l n, h 3 (-
R. J. C'onte, Reactor Inspector ca:e signec
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ca:e signed
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ca:e signed
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Approved by:
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b2% [8 R. R. Keim g, Chi ~ Nuclear Support ca t signec Septfo No. 2
&NS Branch Insoection Summary:
Insoection on May 30 - June 2, 1978 (Recort No. 50-289/78-12)
Areas Insoectec:
Routine, unannouncea inspection of acministrative controls of racility procedures; format and technical content of facility procedures; procedure revisions resulting from Technical Specification Amencments; pro-cedure revisions made in accordance with 10 CFR 50.59(a) and (b); standing orders, special orders, and temporary procedures; and, licensee action on.
orevious inspection findings.
The inspection involved 22 insoector-hours cn site by one NRC inspector.
Results:
Of the six areas inspected, no items of nonccmoliance were found in five areas; :ne a:: parent item of nonc::moliance was found in ene area f:sficiency - f ailure to procerly accrove a temcorary change, :aragrach 5.c),
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Ins::ection Su=.ary
Inscection on May 30 - June 2, 1978 (Recort No. 50-320/78-22)
Areas Ins:ected:
Routine, unannounced inspection of acministrative controls of facility procedures; fontat and technical content of facility procedures; procedure revisions made in accordance with 10 CFR 50.59(a) and (b); and, standing orders, special orders, and temporary procedures.
The inspection involved 15 inspector-hours on site by one NRC inspector.
Results:
No items of nonccmpliance were identified.
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CETAILS 1.
Persons Contacted
'M. Seailla, Unit 2 Plant Operations Review Ccamittee (PORC) Secretary J. Floyd, Unit 2 Supervisor of Operations C. Hartman, Lead Electrical Engineer, PORC Vice Chair an
- G. Kunder, Unit 1 Superintendent, Technical Support G. Lawrence, Instrument and Control Maintenance Supervisor B. Menler, Shift Supervisor
- M. Ross, Unit 1 Supervisor of Operations
- J. Seelinger, Unit 2 Superintendent, Technical Supoort
- M. Shatto, Unit 1 PORC Secretary Several other members of the operations, technical supoort, and administrative staffs were also interviewed.
- denotes these present at the exit interview.
2.
Licensee Action on Previous Inscection Findino
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(Closed) Unresolved Item (2S9/77-23-01):
Resolution of Lcw Flow Alarm Calibration for High Pressure Injection Flow Channels,
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Revision 1, dated November 17, 1977.
Surveillance Procedure SP-1302-5.18, High and Low Pressure Injection Flow Channel, now in-corporates a workable procedure to calibrate the low flow alarm associated with the High Pressure Injection Channels. This cali-bration has been satisfactorily completed en November 23, 1977, and March 30, 1978.
3.
Administrative Centrols of Facility Procedures Administrative controls were reviewed to determine the licensee's system for imolementing requirements associated with the control of facility procedures as specified in Technical Specification, Section 6; Regulatory Guide 1.33, Quality Assurance Program Require-ments; and, ANSI N18.7, Administrative Controls for Nuclear Power Plants.
Areas of emphasis were in the established controls for format, content, review (including periodic review), and approval of facility procedures.
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The following documents were reviewed:
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1001, Revision 3, March 30, 1978, Document Control;
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i 1032, Revision 0, August 29, 1977, Dissemination of Inftrmation;
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and, 1033, Revision 0, September 27, 1977, Operating Memos and
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Standing Orders.
flo items of nonccmpliance were identified.
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4.
Technical Content of Facility Procedures Facility procedures were reviewed on a sampling basis using FSAR System Cescriptions, Piping and Instrument Diagrams and Technical Specifications, where necessary, to verify that procedures were sufficiently detailed to control the cperation or evolution described within Technical Specification Recuirements. The procedures reviewed with respect to this area are marked by asterik (*) in the next
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paragraph (Paragraph 5, Review of Facility Procedures).
5.
Review of Facility Procedures
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Facility pr'ocedures were reviewed on a samcling basis to a.
verify the following:
Procedures, plus any changes, were reviewed, approved,
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and retained in accordance with the requirements of the Technical Specifications and the licensee's administrative controls; The overall procedure format and content were in conform-
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ance with the requirements of the Technical Specifications and AtlSI til8.7, " Administrative Controls for tiuclear Power Plants;"
Checklists, where applicable, were compatible with the
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stepwisa instructions in the procedures;
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Acpropriate Technical Soecification limitations had been included in -he procedures; and, 1566 215
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Temporary changes were made in confor. nance with Technical
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Specification requirc ents and the licensee's administra-tive controls.
(This temporary change review included procedures in addition to those listed below.)
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b.
The following procedures were reviewed:
Unit 1 Procedures Coeratina Procedures 1102-1, Revision 29, May 17, 1978, Plant Heatup to 525'F;
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1103-6, Revision 14, April 25,1978, Reactor Coolant Pump
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Operation; 1104-8, Revision 9, May 9, 1978, Intermediate Cooling
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System;
1106-6, Revision 11, January 5,1978, Emergency Feed;
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1104-19, Revision 2, May 24, 1974, Control Building
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Ventilation System;
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Emercency Procedures 1202-17, Revision 0, September 28, 1973, Loss of Inter-
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mediate Cooling System; 1202-26A, Revision 3, October 26, 1976, Loss of Steam
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Generator Feed to Both OTSG's (Once Through Steam Genera-tors);
1202-268, Revision 3, June 17, 1975, Loss of Steam Generator
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Feed to One OTSG;
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Alarm Resconse Procedures
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Panel E-1-4, Revision 0, July 10, 1974, RC Pump Seal Leak
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Off Flow Hi/Lo;
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Panel D-2-2, Revision 0, July 10,1974, IC (Intermediate
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'coling) System : low Lc; 1566 216
Panel LEFT B-8-4, Revision 0, July 10,1974, Emergency
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Feed Pump Room B Sumo Level High;
Panel A-6-24, Revision 0, July 10,1974, Control Building
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Shif t Foreman Room Fire-Smoke; Maintenance Procedures 1401-Y-1.1, Revision 3, October 25, 1976, RC Pump Seal
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Inspection and Repair;
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1410-C-1, Revision 0, September 29, 1976, Heat Exchanger Inspection and Cleaning; 1401-1.3, Revision 0, November 2, 1973, Reactor Coolant
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Pump Motor Removal and Installation; Unit 2 Procedures Oceratina Procedures
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2102-1.2, Revision 3, February 10, 1978, Approach to
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Cri ticality;
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2107-l.2, Revision 5, May 10, 1978, Class' IE Electrical
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System;
2105-1.1, Revision 1, February 13, 1978, Nuclear Instru-
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mentation; 2105-1.2, Revision 3, May 10, 1978, Reactor Protection
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System; Emeraency Procedures
2202-14, Revision 4, Loss of RC Flew /RC Pump Trip;
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2202-1.1, Revision 3, Reactor Trip;
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Alarm Rescanse Procedures 2204-19.Cl, Revision 1, April 9,1977, DC Bus 2-1 DC
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Voltage Lo; 2204.8.E17, Revision 1, December 27, 1977, Red Channel
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Trip (Channels of the Reactor Protection System are Color Coded);
2204.8.E18, Revision 0, September 14, 1976, Red Channel
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Shutdown Bypass; 2204.8.E19, Revision 1, September 14, 1976, Green Channel
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Trip;
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2204.8.E20, Revision 0, September 14, 1976, Green Channel Tautdown Bypass; Maintenance Procedures
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2405-4.2, Revision 0, Acril 5,1977, 250V CC Breaker
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Maintenance; 2403-1.1, Revision 0, November 8,1977, fluclear Detector
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Removal / Replacement; 2401-1.5, Revision 1, September 8,1977, Use of Freeze
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Seals; Procedures Common to Units 1 and 2 Administrative Procedures 1007, Revision 3, February 13,'1978, Control of TMI
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(Three Mile Island) Records; 1019, Revision 2, December 22, 1975, Qualification of
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Personnel Performing Special Processes;
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Maintenance Procedures
1410-V-20, Revision 0, March 20, 1978, Inspect and
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Repair Butterfly Valves; E-18, Revision 1, October 6,1977, Battery Chargers -
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Annual Inspection; E-3, Revision 1, March 27, 1978, Preventative Maintenance
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Inspection for AC Induction Motors; and, s
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1430-Y-13, Revision 0, January 7, 1977, Flcw Indicator
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Repair and Calibration.
c.
The inspector determined that a Unit 1 Temporary Change (TC)
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had not been reviewed by the Plant Operation Review Committee
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(PORC) nor approved by the Unit 1 Superintendent as of June 1, 1978.
This TC, documented on TC Motice 78-190, affected the
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Reactor Protection System Operating Procedure and became effective May 12, 1978.
The licensee representative could
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not determine why the documentation associated with this TC was not presented to the PORC for review.
Subsequent to the inspector's identification of this noncem-pliance, th'e Unit 1 PORC reviewed and reccmmended for approval TCN 78-190, and the Unit 1 Superintendent approved the change
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on June 2, 1978.
This represents an item of noncemoliance (Deficiency Level)
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with Unit 1 TS 6.8.3.c.
(289/78-12-01)
d.
Temporary Changes (TC) to procedures common to both units, e.g., Administrative Procedures, were reviewed to ensure that
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these changes were approved by a Senior Reactor Ocerator (SRO)
licensed for each unit er by a SRO licensed on both units.
During a review of Unit 2 PORC Meeting Minutes, it was identi-fied that two TC's approved by a SRO, licensed for Unit 1 only, were effective in Unit 2 for approximately two days without approval of a SR0 licensed for Unit 2.
The Unit 2 PORC sub-sequently approved the use of these TC's at Unit 2 and evalt.ated this discrepancy.
(These TC's were judged to be minor in nature.)
As a result of this evaluaticn, responsible :erscnnel were ccunseled en the establisned acministra-ive controls in :nis area.
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The inspector reviewed other TC's for similar circumstances, however, none were identified.
In addition, tne inspector determined that administrative centrols in tnis area are adequate to preclude recurrence assuming personnel follow these procedures.
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The inspector stated that this area will be reviewed in a subsequent inspection to ensure that the implementation of procedures for TC's common to both units is maintained.
No items of noncompliance were identified.
6.
Standing Orders, Scecial Orders, and Temcorary ?rocedures The inspector reviewed licensee Orders / Procedures wnich are cate-gorized as Standing Orders, Special Orders, or Temporary Procedures as defined in ANSI 18.7, " Administrative Controls for Nuclear Power Plants," to determine that:
The content of the Order / Procedure was comcatible with ANSI
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18.7 definitions; and,
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Provisions exist for approval, periodic review, updating, and
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cancellation of these Orders / Procedures.
The inspector identified that the following types' of licensee.
documents were issued in this area:
" Superintendents' Operating Memos;" " Department Operating Memos;" and, "Special Operating Pro-cedures."
No items of noncompliance were identified.
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7.
Changes to Procedures as Described in the Safety Analysis Recort Pursuant to 10 CFR 50.59(a) and (b)
The inspector reviewed licensee records to identify changes to procedures which are described in the Final Safety Analysis Report (FSAR) and to verify that these changes, if any, were reviewed and maintained by the licensee in accordance with 10 CFR S0.59(a) and (b).
Records reviewed were associated with the procedures noted in the previous paragraph (Paragraph 5, Review of Facility Procedures)
and included the licensee's Procedure History File and Onsite Safety Ccmmittee Yeeting Minutes File.
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Of the procedures / changes to procedures sampled, the inscector did not identify any chaage to procedures as described in the FSAR.
It was noted that the licensee has established administrative con-trols for such changes and that these controls do not conflict with 10 CFR 50.59 requirements.
8.
Procedure Chances Resultino from License Amendments Unit 1 License Amendments (22 through 39), which included Technical Specification (TS) Changes, were reviewed to verify that applicable procedures were revised as necessary to reflect these changes.
Amendment 32 effective December 16, 1977, incorporated Fire Pro-tection System Limiting Conditions of Operations / Surveillance Requirements and Administrative Centrols into the Unit 1 TS. The inspector verified that appropriate procedures had been approved and issued covering these surveillance requirements except for certain requirements with a 3 year periodicity.
A licensee repre-sentative stated that these procedures are written, are pending approval, and will be issued shortly.
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The inspector considered this acceptable and stated that this area will be reviewed during a subsequent inspection.
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Unit 2 License Amendments were not reviewed since this has been performed as a part of more frequent operations review conducted since issuance of the operating license February 8,1978.
No items of noncompliance were identified.
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9.
Facility Tour The inspector toured the 'acilities of both units which included the peripheral boundary of the site protected area, turbine build-
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ings, and control rocms. While in the control room, observations of proper manning levels for both day and evening shifts were made and compliance with selected Technical Specification requirements was verified.
No items of noncompliance were identified.
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10.
Exit Interview The inspector met with licensee representatives (denoted in Para-graph 1) at the conclusion of the inspection on June 2,1978.
The inspector sunr.arized the purpose, scope, and findings of the
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inspection.
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