IR 05000322/1982011

Forwards IE Insp Rept 50-322/82-11

ML20054M977
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	07/12/1982
From:	Bordenick B NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
To:	Brenner L, Carpenter J, Morris P Atomic Safety and Licensing Board Panel
References
ISSUANCES-OL, NUDOCS 8207150216
Download: ML20054M977 (4)

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July 12, 1982 In the Matter of Long Island Lighting Company (Shoreham fluclear Pcwer Station, Unit 1)

Docket No. 50-322 (0L)

tiOTE TO ATTACHED SERVICE LIST Enclosed is a copy of NRC Region I Inspection Report 82-11 for your informatio

Sincerely, Bernard M. Bordenick Counsel for NRC Staff

Enclosure:

As stated Distribution:

Bordenick/Dewey/Perlis Black /Repka/Rawson Reis/Lessy Cunningham/Murray Christenbury/Scinto J. Higgans A. Schwencer-116C R. Gilbert /F. Weinkam-330 J. Norris-AR-5008 OELD Formal Files (2)

Chron (2)

Docket Files /PDR/LPDR DFC :0 ELD 0m  : : :

WDD :

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NAME :BBordenick :EReis/s : : : : :

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matte'r of LONG ISLAND LIGHTING COMPANY Docket No. 50-322 (Shorehan Nuclear Power Station, ) .

Unit 1) )

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Lawrence Brenner, Esq.* Ralph Shapiro, Es Administrative Judge Cammer and Shapiro Atomic Safety and Licensing Board 9 East 40th Street U.S. Nuclear Regulatory Commission New York, NY 10016 Washington, Dr. James L. Carpenter *

Administrative Judge Howard L. Blau, Es Atomic Safety and Licensing Board 217 Newbridge Road U.S. Nuclear Regulatory Commission Hicksville, NY 11801 Washington, DC 20555 Dr. Peter A. Morris * W. Taylor Reveley III, Es Administrative Judge Hunton & Williams Atomic Safety and Licensing Board P.O. Box 1535 U.S. Nuclear Regulatory Commission Richmond, VA 23212 Washington, DC 20555 Matthew J. Kelly, Es Staff Counsel New York Public Service Consnission 3 Rockefeller Plaza Albany, NY 12223

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Stephen B. Latham, Es John F. Shea, III, Es Herbert H. Brown, Es Twomey, Latham & Shea Lawrence Coe Lanpher, Es Attorneys at Law Karla J. Letsche, Es P.O. Box 398 Kirkpatrick, Lockhart, Hill, 33 West Second Street Christopher & Phillips Riverhead, NY 11901 1900 M Street, th Floor Washington, Atomic Safety and Licensing i Board Panel * Docketing and Service Section*

U.S. Nuclear Regulatory Commission Office of the Secretary -

Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Atomic Safety and Licensing i

, Appeal Board Panel *

U.S. Nuclear Regulatory Commission Washington, DC 20555 I

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COURTESY COPY LIST Edward M. Barrett, Es Mr. Jeff Smith j General Counsel Shoreham Nuclear Power Station

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Long Island Lighting Company P.O. Box 618 250 Old County Road North Country Road Mineola, NY 11501 Wading River, NY 11792 Mr. Brian McCaffrey MHB Technical Associates Long Island Lighting Company 1723 Hamilton Avenue -

175 East Old Country Road Suite K Hicksville, New York 11801 San Jose, CA 95125 Marc W. Goldsmith Hon. Peter Cohalan Energy Research Group, In Suffolk Cobnty Executive 400-1 Totten Pond Road County Executive / Legislative Bldg Waltham, MA 02154 Veteran's Memorial Highway Hauppauge, NY 11788 David H. Gilmartin, Es Suffolk County Attorney Mr. Jay Dunkleberger County Executive / Legislative Bld New York State Energy Office Veteran's Memorial Highway Agency Building 2 Hauppauge, NY 11788 Empire State Plaza

, Albany, New York 12223

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JUN I8 1982

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REGION I==

Report N /82-11 Docket N License No. CpPR-95 Priority --

Category B Licensee: Long Island Lighting Company .

175 East Old Country Road Hicksville, New York 11801

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Facility Name: Shoreham Nuclear Power Station Inspection at: Shoreham, New York Inspection conducted: May 11-14, 17-20, 1982 Inspector: N.k, 2% 7 8h H. H. Nicholas, Reactor Inspector / date/ signed date signed date signed Approved by:

L. H. Bettenhausen, Chief, Test Program

• k/S/82 date signed Section Inspection Summary:

Inspection on May 11-14, 17-20, 1982 (Report No. 50-322/82-11)

Areas Inspected: Routine unannounced inspection of licensee's action on previous inspection findings; part 21 report followup; preoperational test program status including test program implementation, test prccedure review, procedure verifica-tion, test witnessing, test results evaluation and operations quality assurance procedure audits; and tours of the facility. The inspection involved 72 inspector hours on site by one NRC region - based - inspecto . Results: One violation was identified (Failure to conduct surveillance tests of battery systems). .._

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DETAILS

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1. Persons Contacted Long Island Lighting Company R. Gutman, Maintenance Engineer

J. Kaczor, Assistant Project Engineer

'J. Kelly, Manager, Field Quality Assurance

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W. Klein, Lead Startup Engineer

+* A. Muller, Quality Control Engineer

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J. Rivello, Plant Manager -

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+ D. Terry, Assistant Startup Manager ,

+* R. Werner, Operating Quality Assurance Engineer

E. Youngling, Startup Manager Stone and Webster Engineering Corporation

+ W. Matejek, Lead Advisory Engineer T. Paulantonio, Lead Startup Engineer General Electric Company K. Nicholas, Lead Startup Engineer J. Reilly, Operations Manager U.S. Nuclear Regulatory Commission

+* J. Higgins, Senior Resident Inspector

denotes those present at exit interview on May 14, 198 + denotes those present at exit interview on 'tay 20, 198 . Licensee Action on previous Inspection Findings (Closed) Inspector Followup Item (50-322/81-03-01) Procedure PT 123.001, Standby Liquid Control (SBLC) System, was written on June 21, 197 The most recent General Electric design specification for the SBLC system is document no. 22A1482AJ, revision 3, issued January 17, 198 .. ,

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The inspector noted that the amount of sodium pentaborate called for in the test procedure and the acceptance criteria differed from the amount specified in the G.E. design documen The inspector reviewed G.E. Specification 22A1482AJ, Revision 3, Figure 1, for SBLC Storage Tank Sodium Pentaborate volume and concen-tration limits, and procedure PT 123.001-1, Approved September 4, 198 The irspector verified that the test procedure acceptance criteria reflects current design specifications. This item is close (Closed) Inspector Followup Item (50-322/81-03-02) In reviewing proce-dure PT 119.001, Reactor Core Isolation Cooling (RCIC) System, the .

inspector expressed concern that acceptance criteria in the procedure were marked "later, to be provided at a future date", and that the -

method used to calculate the net positive suction head is not provided in the test procedur The inspector reviewed PT 119.001-1, Approved April 12, 1981. The inspector verified that required acceptance criteria are included and ,

reflect the current design specifications. The inspector verified the addition to the test procedure of RCIC pump minimum NPSH calculations for condensate storage tank to vessel and suppression pool to vessel, in addition to calculations to determine RCIC pump head versus spee This item is close (Closed) Unresolved (50-322/82-04-02) None of the three Emergency Diesel Generator crankcase vents extending from EDG rooms had bird screens installed on them, as is indicated on flow diagram FM 44A-1 The inspector verified the installation of bird screens on all three EDG crankcase vent pipes. This item is close . Part 21 Report Followup 3.1 General In a letter to the Director, Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, dated March 19, 1982, and in accordance with Title 10, Chapter 1, Code of Federal Regulations, Part 21, Transamerica Delaval Incorporated, notified NRC of a potential defect in a component of Standby Diesel Generators. A potential problem exists with the sensing line between the starting air storage tank and the starting air compressor. Air tanks are seismic category 1. The starting air compressor is not seismically supported. The sensing line is not supplied by Transamerica Delaval. On some installations, Transamerica Delaval furnished a seismically qualified manual isolation valve for the sensing line. On installations where the isolation valve was not supplied by Transamerica Delaval, it is not known if the valve is seismically qualified, or if a valve was installed. During.a_. seismic event, the sensing line could fail, causing the starting air pressure to -

bleed down to a point where the engines would not start if require _

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3.2 Scope - i The inspector discussed this with the cognizant engineer and other licensee representatives reviewed the system description and Diesel Generator Air Start flow diagram FM-448-4; and visually inspected all three Diesel Generator Air Start Piping System .3 Findings The following observations and determinations wer: made:

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In each system the starting air compressor, the air dryer .

and associated piping and and sensing line up to the four inch header pipe are non-seismi The four inch header, the four inch check valve, the piping and the starting air storage tank,-are seismically mounted and seismically supporte The starting air storage tank and the four inch check valve

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are seismic category The air pressure sensing line does not connect between the starting air storage tank and the starting air compressor, but rather, connects from the starting air compressor to the four inch piping header. This connection point of the sensing line is between the four inch check valve and the starting air compresso The inspector verified that the four inch check valve was tested for reverse flow and leakage from the starting air storage tank back to and through the compressor to atmos-l phere. This was accomplished successfully during preopera-tional testing of the DG air start system. The starting air l

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storage tank fully charged, the compressor was secured and a section of pipe opened to atmosphere between the four inch check valve and the starting air compresso The inspector verified that this potential deficiency is not a problem at the Shoreham Station. The inspector had no further question . preocerational Test Program 4.1 References:

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SNPS Final Safety Analysis Report

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SNPS Safety Evaluation Report, NUREG-0420, and Supplement 1 I --

SNPS Startup Manual e

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Stone and Webster, Construction Site Instructions, House-keeping .

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SNPS Project Schedules, Startup Disciplines -

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SNPS Startup Monthly Report -

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IEEE 308-1974, Class 1E Power Systems for Nuclear Power

' Generating Stations

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IEEE 387-1972, Diesel Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations

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IEEE 450-1975, Maintenance, Testing, Replacement of Large Lead Storage Batteries for Generating Stations and Substa-tions

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RG 1.9-1971, Selection of Diesel Generator Set Capacity for Standby Power Supplies

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RG 1.32-1977, Safety Related Electric Power Systems for Nuclear Power Plants *

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RG 1.41-1973, Preop Testing of Redundant On Site Electric Power Systems to Verify Proper Load Group Assignments -

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RG 1.68-1977, Initial Test Programs for Water Cooled Reactor Power Plants

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RG 1.93-1974, Availability of Electric Power Sources

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RG 1.108-1977, Periodic Testing of Diesel Generator Units Used as On Site Electric Power Systems

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RG 1.118-1976, Periodic Testing of Electric Power and N Protection Systems

- ' RG 1.128-1978, Installation, Design of Large Lead Storage Batteries for Nuclear Power Plants

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RG 1.129-1977, Maintenance, Testing, Replacement of Large Lead Storage Batteries for Nuclear Power Plants 4.2 Test Program Status and Implementation The inspector met with the Startup Group and other licensee representatives and discussed the status of construction; system turnovers; completed preoperational tests and remaining tests, test procedures approved for testing, awaiting results evaluation, and awaiting review and approval; tests for which results have been evaluated and approved; and completed systems turned over to plant staff. The discussions included the interface between the preoperational test program and the startup test program. The inspector reviewed the monthly startup report, the project schedule startup charts for all disciplines, a test matrix status of tests and test procedures, and plans of the day showing work in progress and tests of components and systems scheduled to start or bcing teste As a result of these discussions and review of documents relative to test program status and implementation, no discrepancies were noted. The inspector had no further question .3 Test Procedure Review, Verification and Test Witnessing 4.3.1 Test Procedure Review and Verification <

The procedures listed below were reviewed in prepsration for test .

witnessing. They were reviewed for technical and administrative -

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adequacy and for verification that adequate testing is planned to - i satisfy regulatory guidance and licensee commitment PT 425.001, Approved April 20, 1981, Primary Containment Inerting System

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PT 119.001-1, Approved April 12, 1981, Reactor Core Isolation Cooling System'

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PT 202.001-1, Approved March 12, 1982, High Pressure Coolant Injection System

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PT 307.0018-1, Approved February 19, 1982, Emergency Diesel Generator 102 - Mechanical -

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PT 307.003B, Approved May 27, 1981, Emergency Diesel Generator 102 - Electrical

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The procedures were reviewed for manual review and approval, procedure format, test objectives, prerequisites, environmental *

conditions, references, initial conditions, test objectives are met, performance verification, recording conduct of test, restora-tion of system to normal after test, identification of personnel conducting and evaluating test data, and independent verification of initial steps or parameters. The inspector ascertained that the procedures are consistent with regulatory requirements, guidance and licensee commitments. Discussions were held with the cognizant engineers in preparation for testing of these systems. Concerns of the inspector were addressed. The inspector had no further question . Test Witnessing Test witnessing by the inspector included the following:

Observations of overall crew performance which included:

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Approved procedure with latest revision available and in used by test personnel;

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A designated person in charge and conducting the test;

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Minimum test personnel requirements met; -

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Qualified personnel performing the test;

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Test precautions followed and prerequisites met;

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QA/QC hold and witness requirements met;

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Proper plant supporting systems in service;

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Special test and measuring equipment required by the test procedure calibrated and in use;

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Procedure is technically adequate for the test;

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Testing performed as required by the test; =

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Test results appear to be acceptable; - r

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All data is collected and properly documented for final analysis; and,

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Criteria for interruption and continuation of testing is adhered t Observations independent measurements and calculations and review of documentation of test results by the inspector indicated that acceptance criteria has been me .3. High Pressure Coolant Injection System (HpCI)

The preoperational test of the HPCI system should demonstrate the capability of the HPCI system to inject coolant into the ~

reactor vessel automatically and reliably in the event of a loss of coolant accident. The test is conducted in three stages: individual component testjng; uncoupled turbine testing; and coupled turbine testin The HPCI system logic tests consist of vacuum breaker isolation .

logic, isolation and trip logic, auto initiation logic, and miscellaneous logic. Portions of the logic testing and valve lineups were witnessed by the inspecto The inspector witnessed the following portions of the HPCI system uncoupled turbine testing: idle speed remote manual ,

trip, local manual trip, vibration readings, stability of turbine control system by increasing speed to low speed for safe operation (2100 RPM) and then to high speed (4000 RPM),

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mechanical overspeed trip, and time lapse and turbine speed for the automatic stop valve rese The inspector made independent mea.urements and calculation The observed results indicated that acceptance criteria had been me No discrepancies were noted. The inspector had no questions on these portions of HPCI testin .3. Emergency Diesel Generator - 102 (EDG)

The preoperational test of EDG - 102 should verify correct operation during its starting, loading, and shutdow The inspector witnessed portions of the EDG - 102 electrical test which included initial manual start, testing of diesel control switches, testing auto start and phase rotation, and testing synchronous operation and two hour rated load capabilit No discrepancies were noted. The inspector had no q0estions on this portion of the emergency diesel generstor testin , ,

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. Long Island Lighting Company 7 4.3.2. EDG Supporting System _ ,

The EDG Service Water System is one of several systems needed for supporting EDG operation. As documented in Inspection Report 50-322/82-04, in section 4.3.2.1, "EDG Service Water System", the inspector observed salt encrus-tation on flanges and top and bottom caps of reliet valves P41-ROV-019A, 0198 and 019C. These valves are installed on the bypass line of the service water outlet from the diesel engine coolers. This condition is indicative of possible internal salt encrustation which could make these valves inoperable. The inspector examined the relief valves and .

verified that all thr ee valves were removed, cleaned, adjusted, tested and reinstalled. The inspector was satis-fied with this corrective action and had no further questions '

on this ite .

4.4 Test Results Evaluation 4. procedures Reviewed .

The preoperational test procedures and acceptance test procedures listed in Attachment A were reviewed to ascertain whether uniform criteria are being applied for evaluating completed preoperational tests to assure their technical and administrative adequac The inspector reviewed the test results and verification of licensee evaluation of test results by review of test changes, test exceptions, test deficiencies, "As-Run" copy of test procedure, QC inspection records, and verifying that the test results have been approve . Findings:

The following unresolved test exceptions were noted in this review:

Procedure Title Exceptions i

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PT 102.001-1 Circ Water 003, 00 PT 123.001-1 SBLC 017, 018, 019, 020, 02 PT 501.002 RSDP Halen 002, 00 PT 622.001 LPMS 002, 004, 00 .

AT 301.001 138 KV 002, 003, 00 AT 670.003 120 VAC UPS INV 001, 00 These procedures will be examined on subsequent inspections for resolution of the listed exceptions and approval by the license This is an inspector followup item (50-322/82-11-01).

In reviewing the completed test procedures for test results evalua-tion and procedure verification, the inspector observed the following:

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Long Island Lighting Company 8 SNPS Startup Manual, section 8.4.2 X1, Exceptions Sheet, - r states, in part, "In this section note any deviation from the indicated tests and explain how the deviation does not invalidate the other sections of this test." In reviewing these procedures the inspector noted that some items in the exception column are annotated and signed off in the disposition column by reference to an Engineering and Design Change Request (E&DCR) which had been written for the item. In reviewing these completed test packages, it was not apparent to the inspector whether the excep-tion had been completed and cleared. This can lead the reviewer

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to believe that the exception is resolved when in fact it is still ope ,

Because this completed test package is the official plant document .

describing the test and the system performance that is reviewed by engineering, station staff, and the NRC for the evaluation of test results, the inspector identified no simple method to allow the reviewers or the inspector to verify the closing of these exception The licensee representative acknowledged the inspector's concern and stated that even though the exceptions are tracked by means of the master punch list and E&DCR's, amplifications would be forth-coming for the Startup Manual and the completed test packages, to document resolved exceptions. This will be examined on a subse-quent inspection and is an unresolved item (50-322/82-11-02).

In review of the test procedure approval dates, test results evaluation review approval dates, and the test dates for the Performance Tests and Service Tests of the batteries, the inspector noted the following:

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The 24 VDC battery A was performance tested and service tested through the period January 14, 1980 to February 15, 198 Test results were evaluated and approved on August 26, 198 The 24 VDC battery B war performance tested and service tested through the period January 17, 1980 to February 25, 198 Test results were evaluated and approved on September 17, 198 The 125 VDC battery A was performance tested and service -

tested through the period July 30, 1980 to September 9, 198 Test results were evaluated and approved on October 22, 198 CFR 50, Appendix B, Criterion XI, requires a test program with written test procedures to demonstrate that systems and components will perform satisfactorily in service, incorporating the require-ments and acceptance limits contained in applicable document '

10 CFR 50, Appendix A, Criterion 18, requires that electrical power systems important to safety, shall be designed to"Be tested periodi- ,

cally for operability and functional performanc .

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- Long Island Lighting Company 9 Shoreham FSAR Section 8.3.2, DC Power Systems, describes a periodic - r test program which includes battery capacity tests. These tests meet the intent of IEEE 308-1971 to determine battery capacit The performance discharge test, as listed in IEEE 308-1971, will be performed according to IEEE 450-1972. "Also, a battery service test as described in IEEE 450-1972 will be performed during refueling outage or at some other outage with intervals between tests not to exceed eighteen months." (FSAR p8-3.44).

Contrary to the above, as of May 20, 1982, battery service testing has not been conducted on the following three batteries within the prescribed eighteen months: .

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The 24 VDC battery A, due to be tested by August of 198 ,

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The 24 VDC battery B, due to be tested by August of 198 The 125 VOC battery A, due to be tested by March of 198 This item is a violation (50-322/82-11-03). .

4.5 Operations Quality Assurance (00A) Procedure Audits The Shoreham 0QA audit group conducts an unscheduled verification activity audit of completed preoperational test procedure package The audit addresses the requirements of the FSAR, SER, Startup Manual, OQA Manual, Regulatory Guides and test procedure The inspector selected, at random, the following sample of completed preoperational test procedure packages that were audited by OQA group:

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PT 117.001-3, Instrument and Service Air Audit Report No. 80-11, Audited March 4-7, 198 Audit Review approved March 10, 198 PT 709.001, Reactor Water Cleanup Audit Report No. 82-22, Audited April 22-30, 198 .

Audit Review approved May 11, 198 PT 136.004, Jet Pump Instrumentation e Audit Report No. 82-21, Audited March 24-30, 198 Audit Review approved May 11, 198 PT 652.001, Power Range Reactor Recirc Flow Units l Audit Report No. 82-15, Audited February 23, 198 Audit Review approved March 1, 1982.

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414.001A-1, B-1, C-1, Diesel Generator Room Ventilati.on System

! Audit Report No. 81-19, Audited June 3, 198 Audit Review approved June 19, 198 ,

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Audit Report No. 81-14, Audited May 14, 198 Audit Review approved May 19, 198 PT 107.002, Demineralized Water Transfer Audit Report No. 82-14, Audited January 13 to February 17, 1982 Audit Review approved February 19, 1982

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PT 41J.001, B-2 Screenwell Pumphouse Ventilation Audit Report No. 82-19, Audited April 22, 1982 Audit Review approved April 22, 198 .

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PT 707.001-1, Fuel Pool Cooling and Cleanup ,

Audit Report No. 82-16, Audited March 11, 198 Audit Review approved April 1, 198 PT 311.001 A, B, C, 480V Emergency Power Distribution Audit Report No. 81-23, Audited December 14, 198 Audit Review approved December 15, 198 The inspector reviewed the above preoperational test procedure packages and verified that they met the acceptance criteria of the test procedures, FSAR documents and applicable regulatory requirements. The inspector had no further question . Unresolved Items Unresolved items are matters about which more information is required to ascertain whether they are acceptable items, items of noncompliance, or deviations. An unresolved item disclosed during the inspection is discussed in Section 4. . plant Tours The inspector made several tours of the facility during the course of the inspection. The tours included the containment, reactor building, turbine building, control structure, control room, battery rooms and diesel generator rooms. The inspector observed work in progress, housekeeping, cleanliness controls and witnessing of tests. No discrepancies were identifie . Exit Interview At the conclusion of the site inspection on May 20, 1982, an exit meeting was conducted with the licensee's senior' site representatives (denoted in Paragraph 1). The inspector summarized the scope and findings of the inspection. Previous inspections in this area were discusse ,

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ATTACHMENT A

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PRE 0PERATIONAL TEST PROCEDURES REVIEWED

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PT 102.001-1, approved August 25, 1981. Test results evaluation approved November 10, 1981. Circulating Water

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PT 107.001-3 approved January 26, 1979. Test results evaluation approved October 22, 1981. Makeup Demineralizer and Transfer

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PT 117.001-3 approved April 20, 1977. Test results evaluation approved *

March 20, 198 Instrument and Service Air

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PT 123.001-1 approved September 4, 1981. Test results evaluation '

approved February 26, 1982. Standby Liquid Control

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PT 129.001 approved January 21, 1981. Test results evaluation approved May 3, 1982. Turbine High Pressure Control

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PT 136.004 approved September 27, 1978. Test results evaluation approved March 12, 1982. Jet Pump Instrumentation

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PT 501.002 approved December 14, 1981. Test results evaluation approved March 30, 1982. Remote Shutdown Panel Room Total Flooding Halon

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PT 315.001A approved July 25, 1979. Test results evaluation approved October 22, 1980. 125 VDC Power Distribution A

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PT 315.001B approved July 25, 1979. Test results evaluation approved June 26, 198 VDC Power Distribution B

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PT 316.001A approved June 20, 1979. Test results evaluation approved August 26, 1980. 24 VDC Power Distribution A

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PT 316.0018 approved June 20, 1979. Test results evaluation approved September 17, 1980. 24 VDC Power Distribution B

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PT 311.001A approved November 14, 1978. Test results evaluation l approved December 14, 1981. 480 V Emergency Bus Distribution A

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PT 311.0018 approved November 14, 1978. Test results evaluation approved December 14, 1981. 480 V Emergency Bus Distribution B

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PT 311.001C approved November 14, 1978. Test results evaluation approved December 14, 1981. 480 V Emergency Bus Distribution C

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Attachment A 2

-- PT 410.001A-3 approved April 23, 1981. Test results evaluation approved _ ,.

June 4, 1981. Battery Room Ventilation A

-- PT 410.0018-3 approved April 23, 1981. Test results evaluation approved June 4, 1981. Battery Room Ventilation B

-- PT 410.001C-3 approved April 23, 198 Test results evaluation approved June 4, 1981. Battery Room Ventilation C

-- PT 414.001A-2 approved May 27, 1981. Test results evaluation approved June 5, 1981. Diesel Generator Room Ventilation A

-- PT 414.0018-2 approved May 27, 1981. Test results evaluation approved June 5, 1981. Diesel Generator Room Ventilation B

-- PT 414.001C-2 approved May 27, 1981. Test results evaluation approved Juen 5, 1981. Diesel Generator Room Ventilation C

-- PT 415.001A-2 approved February 19, 1982. Test results evaluation approved March 12, 1982. Screenwell Pumphouse Ventilation A ,

-- PT 415.0018-2 approved February 19, 1982. Test results evaluation approved March 12, 1982. Screenwell Pumphouse Ventilation B

-- PT 604.001 approved March 15, 1978. Test results evaluation approved January 25, 1982. Average Power Range Neutron Monitoring

-- PT 606.001 approved May 19, 197 Test results evaluation approved January 11, 1982. Rod Blocking Monitoring

-- PT 608.001 approved July 19, 1978. Test results evaluation approved April 20,1982. Rod Drive Control

-- PT 622.001 approved November 9, 1981. Test results evaluation approved February 19, 1982. Loose Parts Monitoring

-- PT 652.001 approved May 16, 1978. Test results evaluation approved February 26, 1982. Power Range Reactor Recirculation Flow Units

-- PT 654.005-1 approved September 11, 1981. Test results evaluation approved December 22, 1981. Drywell Floor Seal Pressure Monitoring

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-- PT 707.001 approved November 9, 1981. Test results evaluation approved January 25, 1982. Fuel Pool Cooling

-- PT 709.001 approved March 15, 1978. Test results evaluation approved March 30, 1982. Reactor Water Cleanup

-- PT 717.001 approved November 25, 1980. Test results evaluation approved May 21, 1981. Liquid Radwaste Discharge Sample Tanks ,

-- PT 710.001 approved November 19, 1980. Test results . approved April 9,1981. '

Low Conductivity Liquid Radwaste

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Attachment A 3

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AT 000.005 approved July 23, 1980. Test results evaluation approved - r July 27, 1981. Cathodic Protection - Diesel Oil Tank and Landside Screenwell Areas

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AT 000.006 approved July 23, 1980. Test results evaluation approved July 30, 1981. Cathodic Protection - Waterside Structures

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AT 000.007 approscd September 18, 1980. Test results evaluation approved August 10, 1981. Condenser Cathodic Protection

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AT 105.001-2 approved October 26, 1977. Test results evaluation approved January 23, 1981. Condensate Storage and Transfer .

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AT 113.001 approved May 9, 1978. Test results evaluation approved .

January 23, 1981. Stator Cooling System

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AT 131.001-2 approved December 17, 1976. Test results evaluation approved August 16, 1978. Well and Domestic Water

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AT 301.001 approved June 17, 1980. Test results evaluation approved -

May 2, 198 KV System

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AT 302.001 approved March 12, 1980. Test results evaluation approved June 12, 198 KV System

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AT 303.001 approved January 17, 198 Test results evaluation approved January 6,1981. Main Generator Transformers

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AT 304.001-1 approved October 18, 1979. Test results evaluation approved November 14, 1980. Normal Station Service Transformer

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AT 305.001 approved October 18, 1979. Test results evaluation approved August 4, 1980. Reserve Station Service Transformer

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AT 313.001A-1 approved April 28, 1978. Test results evaluation approved May 12, 198 VAC UPS Inverter R36-INV-01

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AT 313.0018-1 approved April 28, 1978. Test results evaluation approved June 12, 198 VAC UPS Inverter R36-INV-02

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AT 318.001-1 approved December 11, 1980. Test results evaluation -

approved July 27, 1981. 120 V AC-DC Lighting

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AT 411.001-1 approved August 24, 1977. Test results evaluation approved August 5, 1980. Chemical Lab Heating, Ventilation and AC

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AT 416.001-2 approved November 29, 1980. Test results evaluation approved October 8, 1981. Radwaste Building Ventilation

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AT.670.003 approved January 8, 1980. Test results evaluation approved October 15, 1980. 120 VAC UPS Inverter ~; '- ,

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. Attachment A 4

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AT 670.004 approved December 14, 1979. Test results evaluation approved - *

January 13, 1981. 125 VDC Power to Inverter

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AT 708.001-1 approved March 16, 1978. Test results evaluation approved January 14, 1982. Fuel Pool-Suppression Pool Cleanup

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A7 715.001 approved September 18, 1980. Test results evaluation approved November 17, 1981. Auxiliary Boiler Sample Panel

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AT 715.005 approved August 27, 1980. Test results evaluation approved August 20, 1981. Hypochlorination Sampling

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AT 422.001-1 approved January 8, 1981. Test results evaluation approved October 25, 1981. Hot Water Heating and Glycol System ,

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AT 114.001 approved November 7, 197 Test results evaluation approved November 12, 1979. Generator Isolate Phase Bus Cooling

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AT 125.001-1 approved December 29, 1977. Test results evaluation approved August 12, 1981. Sealing Water System .

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