IR 05000333/1978027
| ML19263B517 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/13/1978 |
| From: | Conte R, Jerrica Johnson, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19263B513 | List: |
| References | |
| 50-333-78-27, NUDOCS 7901180341 | |
| Download: ML19263B517 (12) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-333/78-27 Docket No.
50-333 License No.
OPR-59 Priority Category C
Licensee:
Power Authority of the State of New York 10 Columbus Circle New York, New York 10019 Facility Name:
James A. FitzPatrick Nuclear Power Plant Inspection at:
Scriba, New York Inspection conducted: November 27-30, 1978 Inspectors:
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[ ^ R. 9. ContN, Reactor Inspector date signed
$ Y" to-}is/,1 W.R.JoVnson,ReactorInspector date s Q ned Accompanying H. B. Kister, Chief, Nuclear Support Section Personnel o. 2, 0&fgBranc,h
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date signed
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Approved by:
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CB'. 'KisTef, Chief, NGclear Support dater signed Section No. 2, RO&NS Branch inspection Summary:
Inspection on November 27-30, 1978 (Report No. 50-333/78-27)
Areas Inspected:
Routine, unannounced inspection by regional based inspectors of administrative controls for facility procedures; format and technical content of facility procedures; procedure revisions resulting from Technical Specification Amendments; procedure revisions made in accordance with 10 CFR 50.59(a) and (b);
standing orders; special orders; temporary procedures; and, licensee action on previous inspection findings.
The inspection involved 36 inspector-hours onsite by two hRC regional based inspectors.
Results:
No items of noncompliance were identified.
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Region I t erm 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted
- F. Abbott, Operations Superintendent R. Baker, Maintenance Superintendent
- V. Childs, Assistant to the Resident Manager M. Cosgrove, Site Quality Assurance Engineer J. Ford, Instrument and Control Superintendent S. Hudson, Shift Supervisor J. Leonard, Resident Manager
- R. Pasternak, Superintendent of Power
- D. Tall, Training Coordinator Other members of the operations, maintenance and administrative staffs were also interviewed.
denotes those present at the exit interview
2.
Licensee Action on Previous Inspection Findings (Closed) Followup Item (333/77-16-06):
Establish a Periodicity for Testing the Transversing In-Core Probe (TIP) Shear Valve Cartridges and Circuitry.
The licensee has established a 5 year periodicity in accordance with vendor recommendations to implement F-IMP-7.20, Transversing In-Core Probe Shear Valve Control Circuit Testing and F-IMP-7.21, Transversing In-Core Probe (TIP) Shear Valve Expiosive Actuatirg Cartridge Replacement.
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(Closed) Unresolved (333/77-26-01):
Standby Liquid Control System Squib Charge Surveillance.
Amendment 38, dated July 28, 1978, to the Technical Specifications (TS) revised the criterion for acceptable assurance of operability of the charges for the system squib valves.
The specification was changed to the firing of one charge in a batch of three with the remaining two to be installed in the system.
Prior to this amendment, the TS required the firing of two out of six charges.
The applicable surveillance procedure is consistent with the revised Technical Specifications.
(Closed) Unresolved (333/78-01-01):
Plant Operations Review Committee (PORC) Documentation of Procedure Reviews. At various times during the conduct of the inspection the PORC meeting minutes file was used to verify the PORC review of the sampled operating procedures, temporary procedures and standing orders. None of the discrepancies previously identified under this item were repeated in the meeting minutes issued subsequent to the last inspection of this area.
No items of noncompliance were identifie.
(Closed) Noncompliance (333/78-04-01):
Failure to Complete High Pressure Coolant Injection (HPCI) System Discharge Piping Sur-teillance Test (ST). On February 14, 1978, the licensee completed ST-3H, Revision 0, October 21, 1974, HPCI, RCIC and Core Spray System Discharge Piping Venting When Taking Suction from CST. The data for this test were revieved.
Further additional data for the period Mardh to May, 1978, were reviewed.
based on this, there was no evidence of recurrent failure to perform ST-3H for the HPCI System.
(Closed) Unresolved (333,'78-05-02):
Review, Approval and Deletion of Temporary Procedures (TP's). Approximately twenty-five TP's have been deleted since this item was addressed.
The two effective TP's have been properly reviewed, approved and issued.
(0 pen) Noncompliance (333/78-04-05):
Failure to submit a Licensee Event Report (LER) for a Reportable Occurrence.
LER No. 78-22, dated May 9,1978, was submitted reporting the Low Pressure Coolant Injection Inboard Valve (10-M0V-25A) malfunction on Octeber 4,1977.
The occurrence was reviewed at PORC Meeting No. 78-18 (held March 21, 1978).
The licensee documented that all personnel were instructed to be more prudent in the application of reporting requirements for plant condi-tions associated with reportable occurrences.
The effectiveness of this measure to prevent recurrence will be reviewed by NRC:RI in a subsequent inspection of maintenance activities.
(0 pen) Noncompliance (333/78-04-06):
Failure to Properly Approve the Release for Use of a Nonconforming Part (Cell No. 29) for Station Battery A.
The PORC Meeting No. 78-11 (held February 16, 1978) for-mally documented the approval of release for use of Cell No. 29 into Station Battery A.
The part was in nonconformance due to the lack of documentation from the applicable vendor certifying capacity dis-charge test with acceptable results.
This documentation was received on February 20, 1978, and it was reviewed by the inspector.
The licensee documented that QA/QC staff have reviewed applicable re-quirements and were instructed not to authorize the conditional release of any material without proper documentation and approval.
The effec-tiveness of this measure to prevent recurrence will be reviewed by NRC:RI in a subsequent inspection of maintenance activitie '
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(0 pen) Unresolved (333/78-01-03):
Upgrading of Annunciator Res,'nse Procedure. Along with upgrading these procedures, the licensee is separating the Annunciator Response Procedures from the System Operating Procedures.
The licensee has changed the target completici date of October 31, 1978 to February, 1979 by an internal memoran-dum (See Paragraph 5.d).
3.
Administrative _ Controls for Facility Procedures a.
Administrative controls were reviewed to determine the licensee's system for implementing requirements associated with the control of facility procedures ;s specified in Technical Specification, Section 6; Regulatory Guide 1.33, Quality Assurhnce Program Requirements; 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.
The following documents were reviewed:
AP 1.2, Revision 2, May 19,1977, Plant Operations Review
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Committee;
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AP 1.3, Revision 1, May 19,1977, Control of Administrative Procedures; AP 1.4, Revision 2, February 16, 1978, Control of Plant
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Procedurer;
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AP 1.5, Revision 1, May 26, 1977, Procedures for Rules of Practice;
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AP 2.1, Revision 1, May 19, 1977, Procedure for Operating Procedures;
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AP 2.2, Revision 1, February 2, 1978, Procedure for Emergency Operating Procedures; AP 2.4, Revision 3, August 9, 1978, Procedures for Opera-
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bility Tests;
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AP 3.1, Revision 1, October 31, 1977, Procedure for Maintenance Procedures;
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AP 3.3, Revision 0, April 1, 1977, Procedure for Instru-
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ment Maintenance Procedures; AP 4.1, Revision 1, May 19,1977, Procedure for Department
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Surveillance Tests; and, AP 7.1, Revision 0, April 1,1977, Reactor Analyst Procedures.
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b.
During this review, it was determined that individual departments are responsible for the periodic review of facility procedures (established at 2 year intervals by administrative procedures).
However, AP 1.2, Revision 2, May 19, 1977, Plant Operation Re-view Committee, does not clearly specify a formal program for scheduling and/or documenting these reviews.
Based on discus-sions with selected department heads, it appeared that they are relying on procedure revisions (an entire review of the procedure)
to document evidence of periodic review.
The inspector noted numerous procedures that had been revised since the present licensee was issued the facility licanse in June,1977.
The licensee representative stated that this area would be re-viewed and a formal program for i "ocedure periodic review would be established with AP 1.2 revised accordingly.
This is unresolved pending completion of action i the licensee as stated above, and.ubsequent NRC:RI review (333/78-27-01).
4.
Technical Content of Facility Procedures Facility procedures were reviewed on a sampling basis using FSAR System Desc. iptions, Piping and Instrument Diagrams and Technical Specifications, where necessary, to verify that procedures were sufficiently detailed to control the operation or evolution described within Technical Specifi-cation Requirements.
The procedures reviewed with respect to this area are marked by asterisk (*) in the next paragraph (Paragraph 5, Review of Facility Procedures).
5.
Review of Facility Procedures a.
Facility procedures were reviewed on a sampling basis to verify the following:
Procedures, plus any changes, were reviewed, approved, and
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retained in accordance with the requirements of the Technical Specifications and the licensee's administrative controls;
The overall procedure format and content were in con-
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formance with the requirements of the Technical Speci-fications and ANSI N18.7, " Administrative Controls for NJclear Power Plants;"
Checklists, where applicable, were compatible with the
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stepwise instructions in the procedures; Appropriate Technical Specification limitations had been
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included in the procedura; and, Temporary changes were made in conformance with Technical
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Specification requirements and the licensee's administra-tive controls.
(This temporary change review included procedures in addition to those listed below.)
NOTE:
Review and approval of procedure revisions and changes was conducted only for those issued in 1978 to verify implementation of the licensee's new controls in this area established at the beginning of 1978.
b.
The following procedures were reviewed:
Operating Procedures
- -- F-0P-65, Revision 3, November 16, 1977, Startup and Shutdown Procedure (Section F);
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F-0P-9, Revision 1, July 16, 1975, Main Turbine and Auxil-iaries;
- -- F-0P-13, Revision 4, September 26, 1978, Residual Heat Removal System;
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F-0P-19, Revision 3, April 28,1976, Reactor Core Isolation Cooling System; F-0P-53, Revision 1, November 10, 1975, Drywell Ventilation
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and Cooling; F-0P-2A, Revision 2, December 12, 1975, Feedwater System;
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F-0P-2B, Revision 2, September 28, 1977, Feedwater Control
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System;
F-0P-558, Revision 0, November,1973, Control Room
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Ventilation and Cooling; F-0P-20, Revision 3, March 24, 1976, Standby Gas Treatment
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System; F-0P-43C, Revision 0, November, 1973, LPCI Independent
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Power Supply System; Emeraency/Special Procedures
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F-SP-7, Revision 2, September 22, 1977, Loss of Coolant Flow; F-SP-23, Revision 0, November 6, 1973, Loss of Shutdown
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Cooling; F-SP-10, Revision 1, January 16, 1976, Feedwater Malfunction
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(Decreasing Feedwater Flow);
F-SP-ll, Revision 0, November 20, 1973, Feedwater Malfunction
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(Increasing Feedwater Flow - High Reactor Level);
F-SP-13, Revision 2, November 7,1975, Malfunction of Control
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Rod Drive System;
- Annunciator Response Procedures (Section H of Applicable System Procedure)
Panci 9.3.1-7, RHR A Service Wate-High Radiation;
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-- Panel 9.3.2-32, RHR B Service Water Monitor Downscale;
-- Panel 9.4.1-25, RCIC Turbine Oil Low Pressure;
-- Panel 9.4.1-34, RCIC Turbine Exhaust High Pressure;
-- Panel 09-75 (VA 2-07), Drywell Cooling Fan 68-FN-2B Trouble;
-- Panel 09-75 (VA 2-11), Drywell Cooling System B Return Air Temperature High;
-- Panel 9.5.1-8, Feedwater Control System Signal Failure;
-- Panel 9.5.1-28, Reactor Water Level Pigh/ Low;
-- Panel HV-5B-24, Nuclear Physics Room Temperature High;
-- Panel HV-5A-19, Control Room Return Air Emergency Temperature High;
-- Panel 09-75 (VA 1-16; A-553), Standby Gas Filter Train A Activated Charcoal Absorber Temperature High;
-- Panel 09-75 (VA 2-32; A-544), Standby Gas System Outlet Flow Low;
-- Panel 09-7 (EAS-06), LPCI M0V/ Independent Power Supply B Inverter 3B Loss of A-C Input;
-- Panel 09-7 (EA3-10), LPCI Independent Power Supply INV-3A Major Alarm Shutdown; Maintenance Procedures
-- M10.1, Revision 0, July 1976, RHR Pump Maintenance;
- -- M13.2, Revision 1, September 1976, RCIC Valve Maintenance;
- -- M7.1, Revision 1, July 1976, Containment Control Valve and Vacuum Relief Valve Maintenance;
- -- M2.2, Revision 0, June 1976, Reactor Recirculation Valve Maintenance;
-- M70.1, Revision 0, May 1977, Air Conditioning Water Chiller Maintenance;
-- M8.3, Revision 0, July 1976, Standby Gas Treatment System Filter Replacement;
-- M57.4, Revision 0, May 1978, LPCI Independent Power Supply Charger / Inverter; Administrative Procedures (verification of review and approval only)
-- AP 4.3, Revision 0, April 1,1977, Test and Inspection System;
-- AP 4.1, Revision 1, May 19,1977, Procedure for Department Surveillance Tests;
-- AP 10.1, Revision 0, April 27, 1978, Preventive Mainten-ance Program; and,
-- Operations Department Standing Order No. 4, Revision 2, September 26, 1978, Shift Relief and Log Keeping.
c.
During the review of completed valve line-ups, it was determined that two systems are utilized for the documentation of changes /
exceptions to these lists.
If a change is made to the normal position, as specified by the valve line-up attached to the system procedures, this is considered a temporary change and is administratively controlled for the documentation, review and approval in accordance with Technical Specifications.
If the actual position of the valve is not the same as the listed normal position because of unioue plant conditions, Operation Department Standing Order No. 5, Revision 0, July 7,1978, Valve / Electrical Line-up Checkoff List Review, requires the documentation of such conditions and reason on a form issued by the Standing Order for subsequent review, up to the Operations Superintendent.
A review of completed valve line-ups for the upcoming plant startup (after refueling outage) was conducted to verify the
implementation aspects of the above administrative controls.
In general, it was determined that these controls were being implemented.
However, the valve line-ups for F-OP-3, Condensate System, completed November 19,1978, and F-0P-14, Core Spray System, completed November 18, 1978, had changes to various normal positions or deletion of certain valves. These changes were approved by the onshift supervision in accordance with TS, but it appeared they had not been documented as yet for PORC review ana approval within 14 days.
The licensee representative stated that these line-ups are in the process of being reviewed and appropriate documentation, review and approval will be achieved.
The inspector stated that the line-ups for this startup will be reviewed in a subsequent inspection.
This is unresolvad pending completion of action by the licensee as stated above ad subsequent NRC:RI review within three months (333/78-27-02).
d.
During the review of various procedures, the following items were noted in the area of upgrading operating procedures.
Many system procedures exist that have temporary changes
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dating back to 1975 and 1976.
Except in one case, none of these procedures had been revised.
The licensee representative stated that the present upgrading of system operating procedures should include these temporary changes.
Revision 6 to OP-1, Main Steam System, had been recom-
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mended for approval by PORC but temporary changes, dated March 16, 1978,were not incorporated into this revision.
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OP-9, Revision 1, July 14, 1975, Main Turbine and Auxiliaries, is not in a format consistent with other system operating procedures.
Much of the procedure is system description with minimal procedural aspects coordinating the operation of components within this system.
The licensee representa-tive stated that this particular procedure has been assigned to a shift supervisor for upgrading as a part of the opera-tion's department upgrading of their procedures.
By an internal memorandum from the Operations Superintendent to the Superintendent of Power, dated October 6,1978, it is antic-ipated that the entire department upgrading program (which includes the establishment of separate annunciator response procedures) will be completed by February, 1979.
This is unresolved pending completion of action by the licensee, as stated above, and subsequent NRC:RI review (333/78-27-03).
e.
The inspector noted progress in the upgrading of Surveillance Test (ST) procedures for the Operations Department in light of new STs developed for the Inservice Inspection and Fire Protection Program.
Some STs have dates that are relatively old (prior to 1977) but these were reviewed in the later part of 1977 for any significant changes needed.
In these older STs the inspector noted references to FSAR Sections as requirements for the surveillance test instead of Technical Specifications.
The licensee representative stated that these procedures will be chaned on the next revision of these procedures.
It was noted that the applicable FSAR numbers were similar to TS paragraph numbers.
The inspector considered this acceptable and had no further questions in this are.
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6.
Standing Orders, Special Orders and Temporary Procedures The inspector reviewed licensee Orders / Procedures which are cate-gorized as Standing Orders, Special Orders, or Temporary Procedures as defined in ANSI N18.7, " Administrative Controls for Nuclear Power Plants," to determine that:
The content of the Order / Procedure was compatible with ANSI
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N18.7 definitions; and, Provisions exist for approval, periodic review, updating and
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cancellation of these Orders / Procedures.
The inspector identified that the licensee has issued documents by the same titles in this area.
All effective orders / procedures for the station and each department, issued within the last year, were reviewed.
No items of noncompliance were identified.
7.
Procedure Changes Resulting from License Amendmer.ts License Amendments (32-39), which included Technical Specification (TS) changes, were reviewed to verify that applicable procedures were reviewed as necessary to reflect these changes.
Amendment 34, effective January 31, 1978, incorporated Fire Pro-tection System Limiting Conditions of Operations / Surveillance Recuirements and Administrative Controls into the TS.
The inspector verified that appropriate procedures had been approved and issued covering these surveillanca requirements except for certain require-ments with periodicities equal to and greater than one year.
A licensee representative stated that some of these procedures are in draft form and that they will be reviewed, approved and issued prior to the performance of the applicable surveillance test.
The inspector considered thic acceptable and stated that this area will be reviewed during subsequent inspections.
No items of noncompliance were identifie.
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8.
Changes to Procedures as Described in the Safety Analysis Report FursJant to 10 CFR 50.59 a) and (b)
The inspector reviewed licensee records to identify changes to rocedures which are described in the Final Safety Analysis Report p(FSAR) and to verify that these changes, if any, were reviewed and maintained by the licensee in accordance with 10 CFR 50.59(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 and Onsite Safety Committee Meeting Minutes File.
Of the procedures / changes to procedures sampled, the inspector did not identify any changes to procedures as described in the FSAR.
It was noted that the licensee has established administrative controls to identify such changes and that these controls do not conflict with 10 CFR 50.59 requirements.
9.
Unresolved Items Unresolved items are findings about which more information is required to determine that the item is acceptable, a noncompliance or a deviation. Unresolved items disclosed during this inspection are addressed in Paragraphs 3.b, 5.c and 5.d.
10.
Exit Interview The inspectors met with licensee representatives (denoted in Para-g aph 1) at the conclusion of the inspection on November 30, 1978.
The scope and findings of the inspection were summarized.