IR 05000387/1982026

IE Insp Rept 50-387/82-26 on 820706-09.No Noncompliance Noted.Major Areas Inspected:Overall Startup Program Review, Startup & Hot Functional Test Procedures & Followup on Previous Insp Findings

ML20062E422
Person / Time
Site:	Susquehanna
Issue date:	07/22/1982
From:	Bettenhausen L, Pullani S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20062E401	List: IR 05000387/1982026 ML20062E398
References
50-387-82-26, NUDOCS 8208100100
Download: ML20062E422 (8)

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U. S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No. 50-387/82-26 Docket No. 50-38'i License No. CPPR-101

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Category B Licensee: Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Facility Name: Susquehanna Steam Electric Station, Unit 1 Inspection At: Salem Township, Pennsylvania Inspection Conducted: July 6-9, 1982 Inspectors: , M u #/ [1-V. Pullani

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actor Inspector date Approved By: M vo-H. Bettenhausen, Chief 7/h2/fA date L'.

Test Program Section, Engineering Inspection Branch Inspection Summary:

Inspection on July 6-9, 1982 (Report No. 50-387/82-26)

Areas Inspected: Routine, unannounced inspection of overall startup program review, startup procedure review, hot functional test procedure review, and follow-up on previous inspection findings. The inspectien involved 16 inspector hours in office and 39 inspector hours on site by one region based NRC 'nspecto Results: No violations or deviations were identifie PDR ADOCK 05000387 G PDR

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DETAILS

+ Personnel Contacted 1.1 Pennsylvania Power and Light Company (PP&L)

• F. Butler, I&C Supervisor

• F. Eisenhuth, Senior Compliance Engineer

• J. Green, Operations Supervisor of QA

• R. Harris, Senior Licensing Specialist H. Keiser, Superir tendent of Plant D. Mitchell, Compliance Engineer

• L. O'Neil, Technical Supervisor

• R. Sheranko, Startup Test Group-Supervisor

• D. Thompson, Assistant Superintendent of Plant 1.2 Nuclear Regulatory Commission (NRC)

• J. McCann, Resident Inspector

• Rhoads, Senior Resident Inspector The inspector also interviewed other licensee personnel during the course of inspectio * Denotes those present at the exit interview on July 9, 1982, Follow-up on Previous Inspection Findings (Closed) Inspector Follow-up Item (50-387/82-04-06) Loose Parts Monitoring System

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The licensee is in the process of issuing a new Hot Functional Test Procedure, HF-67-046, Loose Parts Monitoring System, Revision 0, to comply with RG 1.68, Revision 1, Appendix.A, Paragraph 5.n. This item is close (Closed) Inspector Follow-up Item (50-387/82-04-07) Containment Inerting and Purge System The licensee is in the process of issuing a new startup Subtest Procedure, ST 37.2, Containment Inerting, Revision 0, to comply with the requirements of RG 1.68, Revision 1, Appendix A, Paragraph 5.3.3. This item is close (Closed) Inspector Follow-up Item (50-387/82-04-08) Power Ascension Test Plateaus The licensee is in the process of issuing a new Startup Procedure, ST-99,

Master Startup Test Procedure, Revision 0, to specify various Power Ascens. ion Test Plateaus and various startup tests to be performed at each Plateau. The inspector also noted that RG~1.68, Revision 2, Paragraph C.8 permits BWR Power Ascension Tests to be performed at defined Test Conditions rather than at defined power levels. This item is close . . - - - _ _ , _ _

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(Closed) Inspector Follow-up Item (50-387/82-04-09) Shutdown From Outside the Control Room The licensee initiated FSAR Change Request Package PLIS-4014, April 2, 1982, which included correction to the description of test abstract for ST-28, Shutdown From Outside the Control Room, in FSAR Section 14.2.1 This item is close (Closed) Unresolved Item (50-387/82-14-01), Incomplete Informatfor._in Startup Procedure ST-3, Fuel Loading, Revision 0 The licensee issued Revision 1 of the procedure with complete information wherever the word "later" appeared in Revision 0. This item is close (Closed) Inspector Follow-up Item (50-287/82-14-02) Deficiencies in Startup Procedure ST-3, Fuel Loading, Revision 0 The licensee issued Revision 1 resolving all deficiencies identified by the inspector in Inspection Report 50-387/82-14, Paragraphs 2.1.3 through 2.1.11. This item is close (Closed) Inspector Follow-up Item (50-387/82-14-03) Acceptance Criterfun for Maximum Scram Time in Startup Procedure ST-5, Control Rod Drive System, Revision 0 t

The licensee issued Revision 1 of the procedure incorporating the acceptance criterion in step 5.0.3.1.4 and test details in sptes 5.3.4.9, 5.4.4.9, 5.5.4.4, and 5.7. This item is close (Closed) Unresolved Item (50-387/82-14-04) Retesting for Control Rods with Scram Time Outside Two-Sigma Limits l The licensee performed independent calculations to confirm the result of a preliminary calculation showing that retesting of 4 rods will satisfy the requirement of two-sigma limits in RG 1.68, Revision 1, Appendix A, Paragraph 2. This item is close (Closed) Unresolved Item (50-387/82-14-05) Incomplete Information in Startup Test Procedure ST-19, Core Performance, Revision 0 The licensee completed the required information in ST-19, Appendix 19.0-B, K(f) Factor. The procedure is being reissued with the completed informatio This item is close . Startup Test Procedure Review 3.1 _ Scope of Review The startup test procedures listed in Section 3.2 were reviewed for compliance with NRC requirements and licensee commitments. These i

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procedures were reviewed by Plant Operations Review Committee (PORC)

and approved by the Plant Superintendent. Preliminary issues of these procedures were previously reviewed (Inspection Reports 50-387/81-28, 82-04, and 82-14). The present review concentrated on procedure changes subsequent to the preliminary issue .2 Procedures Reviewed

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ST-3, Fuel Loading, Revision 1

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ST-4, Full Core Shutdown Margin, Revision 0

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ST-5, Control Rod Drive System, Revision 1

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ST-14, Reactor Core Isolation Cooling System, Revision 0

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ST-15, High Pressure Coolant Injection System, Revision 0

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ST-19, Core Performance, Revision 0

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ST-25, Main Steam Isolation Valves, Revision 0

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ST-26, Relief Valves, Revision 1

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ST-27 Turbine Trip and Generator Load Rejection, Revision 0

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ST-28, Shutdown from Outside the Control Room, Revision 0 3.3 Findings The inspector's review comments on the preliminary issues of these procedures were satisfactorily resolved by the licensee in the subsequent revisions. All previously identified outstanding items on these procedures are closed. See Section 2. of this repor The inspector noted that the following three appendices in ST-4 are blank and are denoted as "later - GE to provide":

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Appendix 4.1-A, Control Rod Withdrawal Sequence

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Appendix 4.1-0, Control Rod Worths for Shutdown Margin Determination at Initial Criticality

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Appendix 4.1-E, Core Shutdown Keff Versus Core Average Exposure The licensee explained that these appendices were recently received from GE and are in the process of incorporation into ST- This was verified by the inspecto ,

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4. Startup Procedure Verification 4.1 Scope of Verification

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The scope of verification was to ascertain that sufficient test procedures exist for conduct of the Startup Test Program, that the administrative controls for the preparation, review, and approval for the procedures are implemented,-that the test objectives are clearly stated, and that the format and content meet the requirement .2 Procedures Verified

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ST-1, Chemical and Radiochemical Data, Revision 0

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ST-2, Radiation Measurements, Revision 0

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ST-6, SRM Performance and Control Rod Sequence, Revision 0

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ST-7, Reactor Water Cleanup System, Revision-0

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ST-8, Residual Heat Removal System, Revision 0

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ST-9, Water Level Measurements, Revision 1

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ST-10,'IRM Performance, Revision 0

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ST-11, LPRM Calibration, Revision 1

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ST-12, APRM Calibration, Revision 0

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ST-13, Process Computer, Revision 0

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ST-16, Selected Process Tempera *.ures, Revision 1

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ST-17, System Expansion, Revision 0

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ST-18, TIP Uncertainty, Revision 0

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ST-20, Steam Production, Revision 0

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ST-22, Pressure Regulator, Revision 1

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ST-23, Feedwater System, Revision 0

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ST-24, Turbine Valve Surveillance, Revision 1

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ST-29, Recirculation Flow Control System, Revision 1

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ST-30, Recirculation System, Revision 1

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ST-31, Loss of Turbine Generator and Off Site Power, Revision 0

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ST-32, Containment Atmosphere and Main Steam Tunnel Cooling, Revision 0

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ST-33, Piping Steady State Vibration, Revision 0

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ST-34, Rod Sequence Exchange, Revision 0

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ST-35, Recirculati.on System Flow Calibration, Revision 0

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ST-36, Cooling Water Systems, Revision 0

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ST-37, Gaseous Radwaste System, Revision 1

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ST-39, Piping Vibratory Response During Dynamic Transients, Revision 0

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ST-99, Master Startup Test Procedure, Revision 0 4.3 Findings The inspector noted that all Startup Procedures, except ST-31, 32, 36, and sections of ST-99, have been approved by the Plant Super-intendent. ST-31, 32, and 36 are recomme,ded for the approval, but not yet approved. Licensee personnel stated that these procedures would be approved sufficiently in advance of the actual performance of the test The following appendices in ST-33 and ST-39 are blank, indicating that the information is to be supplied by GE.

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Appendix 33.1-A, Main' Steam - Inside Drywell Steady State -

Vibration Data

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Appendix 33.3-A, Recirculation System Steady State Vibration Data

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Appendix 39.1-A, Main-Steam Piping Vibration During TSV Closure Inside Drywell

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Appendix 39.2-A, Main Steam Piping Inside Drywell, Vibration During SRV Operation

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Appendix 39.3-A, Recirculation Piping Vibration During Pump Trips and Restarts The licensee has received this information and is in the process of incorporating it into ST-33 and ST-39. This was verified by the inspector, m

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5. Hot Functional Test Procedure Review 5.1 . Scope of Review The term Hot Functional Test (HFT) usually applies to a PWR where reactor coolant pump heat is used to heat up the plant and check out integrated plant operation under hot conditions prior to fuel loadin Equivalent tests for a BWR are done using nuclear. heat during the Startup phase utilizing applicable Startup Procedures. For Susquehanna 1, the licensee has prepared a set of_ procedures called HFT Procedures, in addition to the regular Startup Procedures. Generally, the purpose of the licensee's HFT procedures is not for check out integrated plant operation under hot conditions; but rather is a set of special procedures for miscellaneous tests or activities such as control system tune-ups, system or component adjustments, etc. , and are performed during Preoperational as well as Startup phases. However, some of the licensee's HFT procedures check out integrated plant operation under hot conditions. Therefore, the scope of review included applicable test procedures, on a sampling basis, from both Startup Procedures and HFT Procedures. The review was to ascertain that the licensee's program complied with the regulatory requirements and licensee commitment .2 Procedures Reviewed 5. Startup Test Procedures

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ST-1.1, Chemistry Data, Revision 0

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ST-7.1, RWCU Blowdown Mode Performance' Verification, Revision 0

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ST-7.2, RWCU Hot Shutdown Mode Performance Verification, Revision 0

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ST-8.3, RHR Shutdown Cooling Mode, Revision 0

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ST-14.1, RCIC Condensate Storage Tank Injection, Revision 0

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ST-14.2, RCIC Reactor Vessel Injections, Revision 0

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ST-14.3, RCIC Rated Pressure Auto Quick Start to Vessel, Revision 0

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ST-14.4, RCIC Low Pressure Auto Quick Start to Vessel, Revision 0

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ST-15.1, HPCI Condensate Storage Tank Injection, Revision 0

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ST-15.2, HPCI Reactor Vessel Injection at Rated Pressure,-

Revision 0

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ST-15.3, HPCI Rated Pressure Quick Start To Vessel, Revision 0

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ST-15.4, HPCI Surveillance Test Demonstration, Revision 0

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ST-25.1, MSIV Functional Test, Revision 0

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ST-26.1, Relief Valve Low Pressure Test, Revision 1

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ST-26.2, Relief Valve Rated Pressure Test, Revision 1 5.2.2 Hot Functional Test Procedures

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HF-45-016, Feedwater Level Control System Tune-up at Test Condition 1, Revision 0

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HF-49-009, RHR Steam Condensing Mode Control System Tune-up, Revision 0

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HF-50-010, RCIC Turbine Control System Tune-up (Hot), Revision 0

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HF-52-011, HPCI Turbine Control System Tune-up (Hot), Revision 0

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HF-55-012, Control Rod Drive Flow Control System Tune-up, Revision 0

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HF-78-003, TIP Alignment and TIP Plotter Adjustment at Rated Temperature, Revision 0

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HF-93-006, Pressure Control System Tune-up at Test Condition 3, Revision 0 5.3 Findings The inspector noted that ST-8.3 RHR Shutdown Cooling Mode, is planned to be performed for the first time at Test Condition 6 (100% power)

which occurs somewhat late in the Startup Test Program. The inspector stated and the licensee agreed that ST-8.3 should be attempted during the earliest available opportunity such as an unplanned plant trip or reactor scram during Power Ascension Testing phas . Exit Interview The inspector met with licensee management representatives (see Section 1 for attendees) at the conclusion of the inspection on July 9, 1982. The inspecter summarized the scope and findings of the inspection at that time.