Text

Forwards Documentation for Review to Support Restart Issues Identified on Unit 2 Startup Commitment List
	ML20137S706
Person / Time
Site:	Point Beach
Issue date:	04/08/1997
From:	Dante Johnson; WISCONSIN ELECTRIC POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NPL-97-0159, NPL-97-159, NUDOCS 9704150223
	Download: ML20137S706 (51)
	v • d • e

. . .

i Wisconsin i Electnc POWER COMPANY >

Point Beach Nuclear Plant (414) 755-2321 6610 Nuclear Rd.. Two Rivers. WI 54241 NPL 97-0159 April 8,1997 Document Control Desk U. S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137 I

Washington, DC 20555 Ladies / Gentlemen:

4 DOCKET 50-jj)1 RESTART DOCUMENTATION POINT BEACH NUCLEAR PLANT. UNIT 2

Pursuant to discussions conducted at a January 31,1997, NRC/ Wisconsin Electric senior management meeting, we are enclosing documentation for review by your staff to sapport restart issues as identified on the Unit 2 Startup Commitment List. The items are:

12: Review 20% of the surveillance procedures associated with safety significant non-pump and valve components (such as heat exchangers and fans) to ensure that the surveillance acceptance criteria satisfy the requirements of the plant design basis / accident analysis.

We are enclosing letter PBM 97-0197 dated March 14,1997, that documents this review. Condition reports 97-0166,97-0548,97-0573, and 97-0574 document fmdings as a result of the review. Also enclosed is the independent review results.

Also enclosed is the Unit 2 Core Load Issues and Unit 2 Startup Commitment List dated April 7,1997.

Sincerely,

[gG - - - -

Douglas F. Johnson ,

Manager- '

l Regulatory Services & Licensing g j MBK/hds 6 Enclosures I cc: NRC Regional Administrator 9704150223 970408 ,

PDR ADOCK 05000301 l P

PDR gggg}((

w nuo,wu n

. .)

l ACTION ITEM STATUS REPORT ' PAGE 1 I s.

- - - - Responsible Person: 04/08/97 l

Trkid: U2R22 RESTART

Urgency: UONE

Action Number: 12

Work Priority: 99 Activity Pending is: DONE ASSOCIATED WITH A COMMITMENT

TITLE AND TASK DESCRIPTION------------------------------------------

Unit 2 Refueling 22 Startup Commitments Prior to leaving cold shutdown review 20% of the surveillance procedures associated with safety si (such as heat exchancers and fans)gnific, ant non-pump to ensure that theand valve components surveillance acceptance criteria saEisfy the requirements of the plant design basis / accident analysis. Make changes as necessary as a result of this review.

DATES---------------------------------------------------------------

Source Commitment:

Record: 01/10/97 ******* Evaluation ********* ****** Correction ** ***

Eval Due: Corr Act Due: 03 21 97

' Action Create:

Action Closed: 04'08'97 01/13/97 Orig Eval Due: Orig CA Due: 02 11 97

/ / Eval Done: Corr Act Done:04 01 97 :

i PEOPLE--------------------------------------------------------------

Responsible for Overall Action: BMS Responsible for Current Pending Activity:

Issue Mana Initia$or:ger:

4 Punchlist Administrator: ...

____..----UPDATE--------------------------------------------------------------

(02/10/97 i Requested Due Date: 02/28/97 (02 ) Changed the Due Date from: 02 I The/11/97 scope...of the review was increased to inclu/11/97 de allto of02/28/97 uhit 2 and all l common components. This will increase the amount of time to do the review.

(02/25/97 .o" " Reviews

~

comoleted '/ou/o? nraft copy of report given to 1

. . _ . . _ e ...m . i __ for comment. There were 61 I urogedures reviewed a.nd 4 condition reports were generated. No major Beficiencies were found. All of unit 1, unit 2 and common were reviewed.

(02/26/97 Requested Due Date: 03/07/97 !

4 (02 Changed the Due Date from: 02 4

The/28/97 responsicle individual mis-interpreted one/28/97 of thetoTet 03/07/97

. Spec I

requirements. More time is required to review procedures involved in the 1 requirement.

(03/07/97 Requested Due Date: 03/21/97 l

" 1 (03/10/97 Changed the Due Date from: 03 !

Resources were not available to work on the co/07/97 mmitment.to 03/21/97 '

(03/19/97 Passed to ; for acceptance of work.

(04 Passed to for Verification.

The/01/97 review of the surveillance procedures was completed. All of unit 1, unit 2 and common procedures were reviewed. The report was issued on March 14, 1997 as PBM 97-0197.

(04/01/97 Passed to for Final Close Out.

Reviewed the) documentation associateu with this review. This is ready for closeout. Condition Reports 97-0166, 97-0548, 97-0573, and 97-0574 were generated as a result of this activity.

(04/08/97 PLA Closure of Item.

d PBM 97-0157 dated March 14, 1997 documents and addresses Commitment #12.

ACTION ITEM STATUS REPORT' PAGE 2 l 04/08/97 i

4

REFERENCES---------------------------------------------------------- r

. PBM 97-0197 CR 97-0166 i CR 97-0548 CR 97-0573 i CR 97-0574

MISCELLANEOUS---------------------- --------------------------------

, . Originating Agency: S stem: XX i - NRC Open Item Nuder: N C Status:

1 Related Outages: U2R22

. Engineering work e: None,Specified Parson Hours: Or ginal Estimate =

Current Estimate =

Actual Hours =

i

?

1 4 '

l 4

4 4

4 i

4 B l i

t i

1 I

I t

i -

i d

INTERNAL i CORRESPONDENCE

I j PBM 97-0197 f To:

From:

Date: March 14,1997 ,

Subject:

RESTART COMMITMENT 12 REPORT f

Copy To: ,,., . , , _ _ , , , ,

.e..

This report is the result of Point Beach Nuclear Plant Unit 2 Restart Commitment #12 and NRC Commitment NRC 96EC #47. This review was. conducted from November 21,1996 through March 12,1997. The original commitment was to review 20 percent of the surveillance !

procedures associated with safety significant non-pump and valve components (such as heat ,

exchangers and fans) to ensure that the surveillance acceptance criteria satisfy the requirements of !

the plant design basis / accident analysis. Calibration, electrical, sampling, Appendix J, inservice ,

inspection program and chemistry procedures were not part of this review. The requirements section does not include all specifications; only the specifications peninent to this review are included. As a result of discrepancies found during the 20 percent review, the scope of the review i was expanded to include all of the Unit 2 and common procedures. Unit I was also completed with this review.

The total number of procedures reviewed was 85 and a list of the procedures is included as l Attachment 1.

The approach taken was,'first, to identify all safety-related components. This was done using a custom printout from CHAMPS. The next step was to get lists of all testing procedures. The list of procedures was then compr. red with the list of safety-related components This resulted in a list of procedures to review. Point Beach Technical Specifications surveillance requirements were also reviewed for any components or systems not listed in the CHAMPS printout.

There were no major changes made to any procedure, nor were there any new procedures created as a result of this review. There will be two tests canceled as a result of this review (see Condition Report 97-0166).

. - . -- = _. - . .. . . . . - - . - - - . - - . - .

.9

PBM 97-0197 March 14,1997 Page 2 There were four condition reports initiated as a result of this review. CR 97-0166 relates to the Containment Accident Recirculation Heat Exchanger. CR 97-00548 relates to the Containment Accident Fan Backdraft Dampers. CR 97-0573 relates to the Emergency Diesel Generator Glycol Coolers. CR 97-0574 ielates to the PAD Battery Room Vent Coolers.

There were two instances of procedures referencing the wrong Technical Specification. The l responsible individuals were notified.

Attachment 2 contains the actual results of the review Attachments i

l l

PBM 97-0197 March 14,1997 Page 3 ATTArilM ENT 1 TOTAL DOCUMENTS REMEWED 85 documents COMMON CMP-10.1, Snubber Component Maintenance Program HPIP 11.54 Control Room. F 16, Filter Testing IT il A, Performance Test for Spent Fuel Pool Heat Exchanger, HX-13 A/B.

IT-560, Leakage Reduction and Preventive Maintenance Program test of Chemical and Volume Control System Holdup Tanks (Refueling)

IT 570, Leakage Reduction and Preventive Maintenance Program test of Dram System OI 92A, Fuel Oil Ordering, Receipt, Sampling and T-173 Fill Tank Draming PC-56.4, HX-10$B Performance Test Battery Room Cooler PC-56.5, HX-105B Battery Room Cooler Performance Test Analysis RMP-37, Diesel Fire Pump Engine Inspection RMP 97, Fire Barrier Penetration Fire Seal Surveillance RMP-58, Containment Fire Seal and Conduit Wrapping Inspection. Unit i RMP 59, Containment Fire Seal and Conduit Wrapping Inspection, Unit 2 RMP-61, Hydraulic Snubber Surveillance and Testing RMP-63, Low Pressure Turbine Rotor Testing RMP-9060 Safety Related Snubber Visual Inspection RMP-9094, Diesel Fire Pump Battery Surveillance TS-09, Control Room Heating and Ventilation Monthly Checks TS-32, Safety Valve Position Verification - Subcooling Margin Computing System - Containment Purge Valve Position TS 71, Monthly Electric Motor-Driven Fire Pump Functional Test TS-72, Annual Fire Pump Capacity Test TS 73, Monthly Fire Protection Control Valve Position Verification TS 74, Annual Underground Fire Main Flow Test TS-75, Biennial Service Testing of Fire Hose and Fire Hose Stations TS-76, Quarterly Automatic Sprinkler and Water Spray System Surveillance Test TS-77, Semi-Annual Smoke Detection System Integrity Test TS-78, Semi-Annual Halon 1301 Fire Suppression System Surveillance Test TS-79, Monthly Surveillance of Fire Hose Stations TS-81, Emergency Diesel Generator G-01 TS-82, Emergency Diesel Generator G-02 TS-83, Emergency Diesel Generator G-03 TS-84, Emergency Diesel Generator G-04 TS40, Sampling of Emergency Fuel Oil Tank, Fuel Oil Storage Tanks and EDG Day Tanks Form PDF-2031, Auxiliary Building Shift Log Form PDF 2033, Turbine Building Shift Log, Unit 2 Safe Load Path and Rigging Manual, SLP-4 Misce!!aneous Heat Exchanger Cleaning and inspection Program GENERIC EPIP 10.3, Post Accident Containment Ventilation System Operation RESP-3.1, PPCS Feedwater Correction RESP-4.1, Test initial Criticality and ARO Physics RESP-4.2, Control Rod Reactivity Worth Measurements RESP-6.2, Precision RCS Flow Rate Measurement RESP 6.5, Reactivity Anomalies

PBM 97-0197 March 14,1997 Page 4 UNIT 1 17 500, Leakage Reduction and Preventive Maintenance Program test of Post Accident Reactor Coolant Sampling System (Refueling) Unit 1 IT-5108, Leakage Reduction and Preventive Maintenance Program test of Safety injection Test Line (Refueling) Unit 1 IT-520A, Leakage Reduction and Preventive Maintenance Program test of Safety injection System (Refueling) Unit 1 17-520B, Leakage Reduction and Preventive Maintenance Program test of ISI-896A&B, St Pump Suction (Refueling) Unit 1 IT-530, Leakage Reduction and Preventive Maintenance Program test of Residual Heat Removal System (Refueling) Unit 1 IT 530A, Leakage Reduction and Preventive Maintenance Program test of Train A HHSI and RHR Systems (Refueling) Unit 1 IT-530B, Leakage Reduction and Preventive Maintenance Program test of Train B HHS! and RHR Systems (Refueling) Unit 1 IT 531, Containment Sump B Suction Line Test (Refueling) Umt i IT 550, Leakage Reduction and Preventive Maintenance Program test of Liquid Chemical and Volume Control System (Refueling)

Unit i IT-580, Leakage Reduction and Preventive Maintenance Program test of Post Accident Containment Atmospheric Sampling System (Refueling) Umt !

IT 590, Leakage Reduction and Preventive Maintenance Program test of Post Accident Containment Vent System (Refueling) Unit i ORT-3, Safety injection Actuation with Loss of Engineered Safeguards AC, Unit 1 ORT-7, Operation of Backdraft Dampers, Unit 1 ORT-61, Sump A Drain to Auxiliary Building Drain, Unit 1 PBTP-040, Performance Test of lHX-15D Containment Fan Cooler, Unit i PC-9 Part 2. Unit i Safeguard Systems Valve and Lock Checklist (Monthly)

PC-56.1, Containment Accident Recire Heat Exchanger Performance Momtoring Test, Unit 1.

TS-3, Main Turbine Stop and Governor Valves with Turbine Trip Test (Quarterly) Unit 1 TS-5, Bi-weekly Rod Exercise Test Unit i TS-33, Surviellance Testing: Containment Accident Recirculation Fan -Cooler Units (monthly). Unit 1 TS-37, Containment Spray Nozzles (Frequency of Less Than or Equal to Five Years), Unit i TS-41, Crossover Steam Dump (Quarterly) Umt i UNIT 2 IT-505, Leakage Reduction and Preventive Maintenance Program test of Post Accident Reactor Coolant Sampling System (Refueling) Unit 2 IT 515B, Leakage Reduction and Preventive Maintenance Program test of Safety Injection Test Line (Refueling) Unit 2 IT 525A, Leakage Reduction and Preventive Maintenance Program test of Safety Injection System (Refueling) Unit 2 IT 525B, Leakage Reduction and Preventive Maintenance Program test of 2SI-896A&B, SI Pump Suction (Refueling) Unit 2 IT 535, Leakage Reduction and Preventive Mamtenance Program test of Residual Heat Removal System (Refueling) Unit 2 IT-535A, Leakage Reduction and Prever.tive Maintenance Program test of Train A HHS1 and RHR Systems (Refueling) Unit 2 IT-535B, Leakage Reduction and Preventive Maintenance Program test of Train B HHS! and RHR Systems (Refueling) Unit 2 IT-536, Containment Sump B Suc' ion Line Test (Refuchng) Unit 2 IT 555, Leakage Reduction and Preventive Maintenance Program test of Liquid Chemical and Volume Control System (Refueling)

Unit 2 IT 585 Leakage Reduction and Preventive Maintenance Program test of Post Accident Containment Atmospheric Sampling System (Refueling) Unit 2 IT 595, Leakage Reduction and Preventive Maintenance Program test of Post Accident Containment Vent System (Refueling) Unit 2 ORT 3, Safety injection Actuation with Loss of Engineered Safeguards AC, Unit 2 l ORT-7, Operation of Backdraft Dampers, Unit 2 l ORT 61, Containment Sump A Drain, Unit 2 l PC-9 Part 3, Unit 2 Safeguard Systems Valve and Lock Checklist (Monthly)

PC 56 2, Containment Accident Recirc Heat E>. changer Perfonaance Monitoring Test, Unit 2.

TS-4, Main Turbine Stop and Governor Valves with Turbine Trip Test (Quarterly) Unit 2 TS-6, Bi-weekly Rod Exercise Test Unit 2 TS 34, Surveillance Testing: Containment Accident Recirculation Fan -Cooler Units (monthly), Unit 2 TS-38, Containment Spray Nozzles (Frequency of Less Than or Equal to Five Years), Unit 2 TS-42, Crossover Steam Dump (Quarterly) Unit 2

PBM 97-0197 March 14,1997 Page5 ATTACHMENT 2 RESULTS OF REVIEW OF SAFETY SIGNIFICANT COMPONENT SURVEll1ANCE TESTS AND INSPECTIONS UNITS I AND 2 EOUIPMENT TESTS & INSPECTIONS HX-015Al-AN/BN/C8/DN - CONTAINMENT ACCIDENT RECIRC HEAT EXCHANGER Reauirements

1. Each fan cooler shall be tested at cach refueling to verify proper operation of the backdraft dampers and the service water bypass valves.

2. . Containment fan cooler accident fans shall be tested monthly to verify operability. Acceptable performance shall be that the accident fan starts and the running current is venfied.

3. Performance testing will be done annually during normal plant operation.

4. The performance of the "D" cooler will be monitored at least once a year.

Desien Basis Per FSAR 5.3.2.2, each cooling coil will transfer 50 00 Mbtu/hr for design basis conditions w hen supplied with 1000 gpm cooling i water @ 70 F. inlet temperature.

Wisconsin Electric Safety Evaluation Report 96-055 and Westinghouse Safety Evaluation Checklist 96-067 changed the design basis to allow for the heat transfer of 37.50 Mbtu/hr per cooling coil.

References TS 15.3.3.B.2 TS 15.4.5.1.C.2 Generic Letter 89-13 PBM 92-0088 Ie, st Procedure ORT-7, Operation of Backdraft Dampers. Unit 1 ORT-7, Operation of Backdraft Dampers, Unit 2 TS 33, Surveillance Testing: Containment Accident Recirculation Fan -Cooler Units (monthly), Unit 1 TS-34, Surveillance Testing: Containment Accident Recirculation Fan -Cooler Units (monthly), Unit 2 PC-56.1, Containment Accident Recirc Heat Exchanger Performance Monitoring Test, Unit 1.

PC 56.2, Containment Accident Recire Heat Exchanger Performance Monitoring Test, Unit 2.

PBTP-040, Performance Test of IHX-15D Containment Fan Cooler, Unit i Unit 2 performance test to be wntten.

Desian Basis Testing Achieved TS-33/34 adequately tests for items 2 and part of I above (procedures do not test fan start if fan is already running. see Condition Report 97-0726). ORT-7 tests the backdraft dampers. The ORT-7 test method differs between unit I and unit 2 coolers.

Unit i ORT-7 was revised in 1993 to more accurately simulate the fan operation during a real accident. Condition Report 97-0548 was initiated on 2/18/97 to address the condition.

For item 3, PBTP-040 adequately tests the performance of the coolers for unit 1. PBTP-040 will be rewritten and re-numbered for use on unit 2. It will be performed in the spring of 1997. The tests will be classified as TS tests to insure that they will receive timely review and attention.

PC-56.1 and 2 should be canceled as they do not adequately test the cooling coils. Condition Report 97-0166 initiated.

. . 1 PB M 97-0197 i March 14,1997 i Page 6 SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEMS R_equirements

1. At least every refueling, verify by visual mspection each containment sump suction inlet is not restricted by debris and the debns stramers show no signs of structural stress or abnormal corrosion J

2. Verify each manual, power operated and automatic valve necessary to insure system operabilit in the emergency core cooling and containment spray systems that is not locked, scaled or otherwise secured in position, is ir the correct position at least once every 31 days.

. Design Basis See Requirements.

Rs.ference TS 15.4.5.11.B Igst Procedure ORT-61, Sump A Drain to Auxiliary Building Drain, Unit 1 ORT-61, Containment Sump A Drain, Unit 2 j

PC-9 Part 2, Unit 1 Safeguard Systems Valve and Lock Checklist (Monthly) l PC 9 Part 3, Unit 2 Safeguard Systems Valve and Lock Checklist (Monthly) I Desinn Basis Testine Achieved

1. Step 4.1 and 4.2 in both Umt I and 2 ORT-61 cleans the sump floor and cleans and inspects the sump screen 2 The purpose of PC-9, Parts 2 and 3 is to scrify valvt positions in the cmergency core cooling and containment spray systems CONTAINMENT SPRAY NOZZLES l Reauirements !

The spray nozzles shall be checked to verify that they are not obstructed at intervals not exceeding five years. l D_gsien Basis See Requirements.

Reference TS 15.4.5.1.B.3 Test Procedure TS-37, Containment Spray Nozzles (Frequency of Less Than or Equal to Five Years), Unit i TS 38, Containment Spray Nozzles (Frequency of Less Than or Equal to Five Years), Unit 2 Desien Basis Testing Achieved Service air is supplied to the spray header and streamers on a reach pole are verified to move by air flowing out of the nozzles.

. . _. . __ . _ _ . . _ . _ . . . _ _ _ _ _ _ - _ - _ . . _ _ _ _ . _ . _ . . _ . . _ . . ~ . . _ _ . _ _ . . _ _ _ _

PBM 97-0197 March 14,1997 Page 7 CONTROI. RODS Reauirements Partial movement of all rods every two weeks Design Basis See Requirements References TS Table 15.4.1-2 Item 10 Tsst Procedure !

TS 5, Bi-weekly Rod Exercise Test Unit 1 TS-6. Bi weekly Rod Exercise Test Unit 2 Design Basis Testing Acl}ieved The purpose of TS-5 and TS-6 is to exercise all control rods TURBINE STOP AND GOVERNOR VAINES Requiremg_nn n Venfy that the turbine stop and governor valves function annually p_esian Basis j See Requirements. I i

i Reference I l TS Table 15.4.1-2 Item 18 l Icst Procedure -

TS-3, Main Turbine Stop and Governor Valves with Turbine Trip Test (Quarterly) Unit 1 TS-4, Main Turbine Stop and Governor Valves with Turbine Trip Test (Quarterly) Unit 2 i i

Design Basis Testina Achieved

)

Section 4 of TS-3 and TS-4 adequately test the smooth operation and alarm functions. position indication and lights of the main j turbine stop and governor valves. l l.

r. LOW PRESSURE TURBINE ROTORS l

l Reauirements l Perform visual and magnetic particle or liquid penetrant tests on the low pressure turbine rotors every five years.

t Desian Basis -

See Requirements.

Referengs -

1 TS Table 15.4.12 Item 19 1 Test Procedur.s RMP-63, Low Pressure Turbine Rotor Testing l-l l

i

. . - ,. ~

a l

PBM 97-0197 I March 14,1997 j

Page 8 Desien Basis Testine Achieved RMP-63 provides direction on where to perform the visual, mag particle and liquid penetrant testing. The procedure also requires the performer to record the Westinghouse Process Specification used for the examination.

BORIC ACID SYSTEM' Reauirements Verify storage tank and piping temperatures 2 temperature required by Table 15.3.2 1.

.Desien Basis Table 15.3.2 1 Enference TS Table 15 4.12 Item 20

' Test Procedure PDF 2031, Auxiliary Building Shin Log Desien BasisTestine Achieved PBF 2031 verifies that the beric acid heat tracing circuits are working and that the boric acid storage tanks are between 80-120* F.

The Tech Spec required weight percent in the boric acid tanks is 23.5 and <4.0. NP 3.2.2, Primary Water Chemistry Monitoring Program, administratively controls the limits to 23 6 and <3.9. Tech Spec Table 15.3.2-1 requires a minimum temperature of 62.5* F. for the percentage required.

POST ACCIDENT RECOVERY SYSTEMS OUTSIDE CONTAINMENT Reauirements Evaluate the integnty of the post accident recovery systems outside the containment each refueling outage.

Desien Basis See Requirements.

Reference TS Table 15.4.12 Item 22 i

Test Procedure j EPIP 10.3, Post Accident Contat.unent Ventilation System Operation ,

IT-500, Leakage Reduction and Preventive Maintenance Program test of Post Accident Reactor Coolant Sampling System !

(Refueling) Unit I i IT 505, Leakage Reduction and Preventive Maintenance Program test of Post Accident Reactor Coolant Sampling System !

(Refueling) Unit 2_ ,

i IT 510B, Leakage Reduction and Preventive Maintenance Program test of Safety injection Test Line (Refueling) Unit 1 IT 515B, Leakage Reduction and Preventive Maintenance Program test of Safety injection Test Line (Refueling) Unit 2 IT 520A, Leakage Reduction and Preventive Maintenance Program test of Safety Injection System (Refueling) Unit 1 !

IT-5208, Leakage Reduction and Preventive Maintenance Program test of ISI-896A&B, SJ Pump Suction (Refueling) Unit 1 IT 525A, Leakage Reduction and Preventive Maintenance Program test of Safety Injection System (Refueling) Unit 2 IT-525B Leakage Reduction and Preventive Maintenance Program test of 2SI-8%A&B, SI Pump Suction (Refueling) Unit 2 1T-530, Leakage Reduction and Preventive Maintenance Program test of Residual Heat Removal System (Refueling) Unit I !

IT 330A, Leakage Reduction and Preventive Maintenance Program test of Train A 101S1 and RHR Systems (Refueling) Unit 1 IT 530B, Leakage Reduction and Prever*ive Maintenance Program test of Train B HHSI and RHR Systems (Refueling) Unit i IT-531 Containment Sump B Suction Line Test (Refueling) Unit 1 IT 535, Leakage Reduction and Preventive Maintenance Program t< i of Residual Heat Removal System (Refueling) Unit 2 IT 535A, Leakage Reduction and Preventive Maintenance Program test of Train A HHS! and RHR Systems (Refueling) I! nit 2 l

PBM 97-0107 March 14,1997 Page 9 IT-5358, Leakage Reducuon and Preventive Maintenance Program test of Train B HHSI and RHR Systems (Refueling) Umt 2 IT 536, Containment Sump B Suction Line Test (Refueling) Umt 2 IT-545B, Leakage Reduction and Preventive Maintenance Program test of Containment Spray System with the Unit in CSD and Defueled Conditions, Unit 2 i

IT-550, Leakage Reduction and Preventive Maintenance Program test of Liquid Chemical and Volume Control System (Refueling)

{

Unit 1 IT-955, Leakage Reduction and Preventive Maintenance Program test of Liquid Chemical and Volume Control System (Refueling)

Unit 2 IT-560, Ler.kage Reduction and Preventive Maintenance Program test of Chemical and Volume Control System Holdup Tanks (Refueling)

IT-370, Leakage Reduction and Preventive Maintenance Program test of Drain System IT 580, Leakage Reduction and Preventive Maintenance P:ogram test of Post Accident Contamment Atmospheric Sampling System (Refueling) Unit 1 IT-585, Leakage Reduction and Preventive Maintenance Program test of Post Accident Contammcnt Atmosph:ric Sampling System (Refueling) Unit i IT-390, Leakage Reduction and Preventive Maintenance Program test of Post Accident Containment Vent System (Refuchng) Umt 1 IT-595, Leakage Reduction and Preventive Maintenance Program test of Post Accident Containment Vent System (Refueling) Unit 2 Desian Basis Testina Achieved The procedures listed atave satisfy the requirements to evaluate the integrity of the post accident recovery systems outside the containment. The tests are performed each refueling outage. j l

IT-545A, Leakage Reduction and Preventive Maintenance Program test of Containment Spray System with the Unit in CSD and l Defueled Conditions. Unit 1, has not been prepared yet. The containment spray system is being added to the recirculation phase. I l

IT-580 and IT-585 proside instructions for pressure testing the post accident recovery systems outside the containment. There is no practical method of pressure testing the hydrogen recombiner which is located in Memphis, Tennessee. EPIP-10.3 performs a pressure test on the recombiner prior to use.

CONTAINMENT PURGE SUPPLY AND EXH AUST VALVES Reauirements Verify that the containment purge supply and exhaust isolation valves are locked closed monthly.

Desien Basis See Requirements.

Iteference TS Table 15.4.1-2 Item 23 i Test Prote.d_un l TS-32, Snfety Valve Position Verification - Subcooling Margin Computing System - Containment Purge Valve Position (Monthly)

Design Basis Testing Achieved Section 4.3 of TS 32 verifics that the control switches for the valves are red locked and notes the Red Lock Number.

l i

I

' I

. i l

PBM 97-0197 )

March 14,1997 Page 10 CROSSOVER STEAM DUMP VALVES l

Reouirements l Verify the operability of each crossover steam dump valve quarterly.

Desien Basis Valves must open in less than 4 seconds.

Reference TS Tabic 15.4.1-2 Item 29 Test Procedur_c l TS-41. Crossover Steam Dump (Quarterly) Unit 1 TS-42. Crossover Steam Dump (Quarterly) Unit 2 Desien Basis Testine Achieved The purpose of TS-41 and 42 are to test the operability of the crossover steam dump valves. All crossover steam dump valves are opened and timed. ;

l COMMGN EOUIPMENT TESTS & TESTS )

F-016 - CONTROL ROOM CllARCOAL FILTER I

I Bgquirements TS 15.4.11

1. At least once per year the pressure dn p across the combined HEPn filters and charcoal absorber banks shall be demonstrated to be less than 6 inches of water at design flow rate.

]

2. The control room emergency filtration automatic initiation shall be demonstrated at least once per year. i

3. The control room emergency filtration shall be operated at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month.

l 1

TS 15.3.12

i. The results ofin-place cold DOP and halogenated hydrocarbon tests, per 15.4.11, shall show a minimum of 99% DOP removal ;

and 99% halogenated hydrocarbon removal. !

2. The results oflaboratory charcoal adsorbent tests, conducted in accordance with Specification 15.4.11, shall show a minimum of 90% removal of methyl iodide. Iflaboratory analysis for in-place charcoal indicate less than 90% methyl iodide, this 4 specification may be met by replacement with charcoal adsorbeat which has been verified to achieve 90% minimum removal !

and which has been stored in scaled containers, and retesting the charcoal adsorber back for halogenated hydrocarbon ;

3. The results of fan testing, conducted in accordance with specification 15 4.11, shall show operation within 10% design flow. l Desien Basis See Requirements.

Reference TS 15.4.11 TS 15.3.12 Test Procedure TS-9, Control Room Heating and Ventilation Monthly Checks HPIP 11.54, Control Room. F-16, Filter Testing

PBM 97-0197 March 14,1997 Page 11 l

! Design Basis Testing Achieved TS 15.4.Ii

1. Step 5.4 of HPIP 11.54 records the pressure drop across the HEPA and charcoal filters and notifies the DSS if the AP exceeds o inches of water.

2. TS-9 verifies that emergency filtration automatic initiation occurs for both of the radiation detectors monthly l 3. Each of the cleanup fans are raq for five hours every month per TS-9.

l TS 15.3.12.

!: 1. Step 5.5 of HPIP 11.54 performs the DOP and Freon testing states that the tests must show > 99% DOP and Freon removal.

l The Step also states that testing must be done at design velocity 20% .

l

2. Step 5,2 of HPIP 11.54 removes charcoal samples and 3.2 states that if the methyl iodide efficiency falls below 95% the charcoal absorbers will be replace with fresh ones and be retested in accordance with Tech Specs.

3. Step 5.3 of HPIP 11.54 performs fan flow rate tests and venfics flow rates within 110%

NOTE: HPIP 11.54 is a cover procedure which records the fan and charcoal parameters. The actual testing is done by a contractor (NUCON) using contractor procedures.

Refer to Condition Report 97-0766.

HX-013A/B - SPENT FUEL, POOL H EAT EXCHANGERS Reauirements The response of Wisconsin Electric to Generic Letter 89-13 states that the spent fuel pool HX will be instrumented to monitor the heat transfer capability. The ocrformance will be monitored at least once a year. .

Design Basis Per FSAR table 9.3 3, the nominal design heat transfer is 15.5 MBlu/hr per heat exchanger. .

Reference Generic Letter 89-13 l PBM 92-0088 I

Test Procedure IT ll A, Performance Test for Spent Fuel Pool Heat Exchanger, HX 13A/B.

l Desien Basis Testinn Achieved The heat exchanger transferred 20.4 MBtu/Hr at test conditions. A heat transfer of 18.9 MBlu/hr was calculated at design I conditions although the calculation method was not reviewed or verified (See Condition Report 96-1201).

j. !

l l

1

l l

l PBM 97-0197 i March 14,1997 Page 12 SFP - SPENT FUEL POOL STRUCTURE n

Reauireme_n.Ls Water level verification weekly.

Desien Basis Low level alarm at 59'10" Reference TS Table 15,4.1-2, Item 7 Test Procedure Form PDF 2031, Auxiliary Building Shift Log Desian Basis Testina Achieved The water level is monitored every shift, The log states that the range is 63' to 64'. The log also states that monitoring the SFP level is a Technical Specification requirement.

IfX-105A/B - PAB BATTERY ROOM VENT COOLERS Reauirement; HX-105B will be monitored at least yearly to check for reduction in performance.

Desien Basis Refer to Condition Report 97-0402.

Reference Generic Letter 89-13 PBM 92-0088 Test Procedure PC 56.4, HX 105B Performance Test Battery Room Cooler PC-56.5, HX 105B Battery Room Cooler Performance Test Analysis.

DesignHasis Testine Achieved No. The instrument accuracy is not good enough for the small temperatures differences involved. The tube and fin material cannot M modeled accurately in the analysis software so approximations must be made. In response to Generic Letter 89-13, Wisconsin

)

l stric commined to monitor the coolers. The testing method has been changed to clean and eddy current test. Condition Report '

97-0575 has been initiated to address the condition.

I l

l l

l I

1 e .

PBM 97-0197. !

March 14,1997 Page 13 FIRE PROTECTION SYSTEM B_eautremenjs A. Fire suppression systems 1 Fire main loop water supply

a. Flow path valve position venfication hivathly

b. Fire pump functional test Monthly

c. Fire pump capacity test Yearly

d. Diesel driven fire pump engine (1) Fuel volume verification Monthly (2) Diesel fuel sample analysis Quarterly (3) Periodic inspection 18 months

c. Diesel driven fire pump battery and charger (1) Battery voltage verification Weekly *

(2) Electrolyte level Weekl)

(3) Electrolyte specific gravity Quarterly (4) Periodicinspection 18 months

2. Water sprinkler systems

a. Flow path vah e position verification Monthly

b. Inspector's test Yearly

c. Visual header and nozzle inspection 18 months

3. Fire hose stations

a. Visualinspection Monthly b Hose hydrostatic test 2 years

c. Valve cycle test 3 years

d. Halon gaseous suppression systems

a. Halon quantity verification 6 months

b. Functional test Yearly

c. Visual header and nozzle inspection Yearly D. Fire detection

1. Fire detection system a Channel functional test 6 months C.- Fire barriers

1. Fire barrier penetration seals

a. Visualinspection 18 months 1

Qpsien Basis j See Requirements. !

l

l Referenes l TS 15.3.14 )

TS 15.4.15 I

l

PBM 97-0197 March 14,1997 Page 14 Tgst Procedure PBF 2033, Turbine Building Shift Log, Unit 2 RMP-37, Diesel Fire Pump Engine Inspectiva RMP-57, Fire Barrier Penetration Fire Seal Surveillance RMP-58, Containment Fire Seal and Conduit Wrappmg inspection, Unit i RMP-59, Containment Fire Seal and Conduit Wrapping Inspection Umt 2 RMP-9094, Diesel Fire Pump Battery Surveillance TS-70, Monthly Diesel Engine-Driven Fire Pump Functional Test TS 71, Monthly Electric Motor-Driven Fire Pump Functional Test TS 72, Annual Fire Pump Capacity Test TS-73, Monthly Fire Protection Control Valve Position Verification TS-74, Annual Underground Fire Main Flow Test TS-75. Biennial Service Testing of Fire Hoses and Fire Hose Stations TS-76, Quarterly Automatic Sprinkler and Water Spray System Surveillance Test TS-77, Semi-annual Smoke Detection System Integrity Test TS-78, Semi-annual Halon 1301 Fire Suppression System Surveillance Test TS 79, Monthly Surveillance of Fire Hoses TS-80, Sampling of Emergency Fuel Oil Tank (T-72), Fuel Oil Storage Tanks (T-175 A) and EDG Day Tanks (T31 A,B & T-176A,B)(Quarterly)

Desian Basis Testine Achieved A.I.a & A.2.a - TS-73 verifies the position of the fire protection system header, section, isolation and sprinkler valves.

A.1 b - TS-70 and TS-7I adequately test the fire pmr as for operability. Pump curves were developed during acceptance testing l when the fire pumps were replaced in 1985 and 1986 i A.I.c - TS-72 tests for the capacity of both fire pumps. r iver speed, nbrations and hydraulic performance are measured and

! compared to acceptance enteria.

A.I.d(l) - PDF-2033 verifies that the diesel fire pump fuel oil tank is between 3/4 and 7/8 full. This is verified every shift. TS-70 l- verifies fuel oil level monthly after the functional test. TS 70 states to fill to a max of 3/4 full after a 30 minute run. PBF-2033 l- states that the level should be 3/4 to 7/8 full. Notified systern engineer. He was aware of the confusion and is going to question operations . 1 A. I d.(2) - TS-80 provides direction to sample the safety related diesel fuel oil tanks. The procedure also provides the acceptance !

criteria for the fuel oil analysis.

l I

A.l.d(3)- RMP-37 uses the manufacturer's manual to inspect the diesel engine.

l l A.I.e(l)- PDF 2033 verifies that the diesel fire pump A and B battery voltages are above 24 volts. This is verified each shift. l l

A.I.c(2) - PBF-2033 verifies that the battery electrolyte level is above the plates. This is verified each swing shift.

PBF 2033 states that the lesel is above the plates but TS-70 states that it must be 3/8" above the plates. Nottfied the system engineer. He will question operations. 1 A.I.e(3) - RMP 9094 annually measures and records specific gravity for all cells of both diesel fire pump batteries.

1 A.I.c(4) - RMP-9094 annually inspects the dicsci fire pump batteries for damage and connection tightness, cleanliness and corrosion free.

f I

A.2 b - TS-76 verifies that w hen the test sprinkler valves are opened, the flow switch will alarm in the control room in less than 90 seconds.

A.2.c TS-76 casures that all sprinklers and spray nozzles are operable and that all other system components are free of damage or defect.

PBM 97-0197 March 11,1997 Page 15 A.3.a. b & c TS-79 verifies the operability , availability and accessibihty of the Tech Spec fire hose stations TS-75 cycles all Tech Spec fire hose reel conttol valves and hydro tests all fire hoses.

A.4 a, b & c - TS-78 tests the halon fire suppression system functions and directs the operator to inspect the nozzles and system components. The test also does an agent quantity surveillance. The quantity venfication states to investigate if the measured quantity is less than 5 umts of original but it does not state where to find w here the original quantity can be found. Notified system engineer. He will question operations.

B.1.a - TS-77 verifies the integrity of the smoke detection system. The test is performed every Apnl and October on all Tech Spec related smoke detectors TS-78 tests the smoke detectors associated with the halon system every March and September.

C.I.a - RMP-57,58 and 59 provide guidance for inspecting the fire barrier '- Hh umts and common. The unit I and 2 tests are presently done yearly to coincide with the outages.

G-01/02/03/04 - EMERGENCY DIESEL GENERATOR BSgtyrpments TS 15 4.6 '

!. Manually start and load each EDG monthly. Load not to exceed 2850KW. Minimum run time of thirty minutes.

2. Auto start, load shed and specific equipment operation initiated by an actual interruption of AC power supplies to ESF busses and a simulated St. After 5 minutes minimum, automatic load shedding and restoration of vital loads are tested again by manually tripping the EDG output breaker. Each refueling outage.

3 Proper operation of Emergency lighting, including automatic transfer switch for DC lights, will be demonstrated each refuchng shutdown.

4. Each EDG shall be inspected following the manufacturer's recommendations for stand-by service.

5. Operability of the dicsci fuel oil system shall be venfied monthly.

6. A diesel fuel oil program shall be maintained to test both new fuel oil upon receipt and stored fuct oil on a quarterly frequency in accordance with ASTM standards.

TS Table 15.4.1-2 Item 17 Perform daily EDG fuel oil supply inventory Design Basis J

See Requirements. )

f Bterc.ncs TS 15.4.6 l Test Procedure Form PBF-2033. Turbine Building Shift Log. Unit 2 TS-81 Emergency Diesel Generator G-01 i TS-82, Emergency Diesel Generator G-02 TS-83, Emergency Diesel Generator G-03 !

TS-84 Emergency Diesel Generator G-04 i ORT-3, Safety injection Actuation with Loss of Engineered Safeguards AC, Unit 1 l ORT-3, Safety Injection Actuation with Loss of Engineered Safeguards AC, Unit 2 TS-80, Sampling of Emergency Fuel Oil Tank (T-72), Fuel Oil Storage Tanks (T-175 A) and EPG Day Tanks (T31 A,B & T-176A B)

(Quarterly)

OI-92A, Fuel Oil Ordering, Receipt, Sampling and T 173 Fill Tank Draining i

l

PBM 97-0197 March 14,1997 Page 16 Manufacturer's Recommendations RMP 9043 series, Diesel Generator Preventative Mamtenance Procedures RMP 93xx scrics, Air Start Equipment Overhaul Procedures .

ICP 13.007A-1/2, G-01/02 I&C Diese! Outage Calib !

ICP 13.0078-1/2, G-03/04 I&C Diesel Outage Calib !

ICP 06.069/070, G-03/04 !&C Non-outage Calib i l

Desinn Basis Testing Achieved 15.4.6

1. TS-81,82,83 and 84 starts and loads the diescis to 2500 to 2700 kW. The procedures run the dicscis for one hour. ;

2. I The NRC reviewed ORT-3 during the OSTI inspection in December,1996. The following is an excerpt from the exit meeting report. "During a review of surveillance testing, which primarily focused upon the EDGs, NRC identified that ORT-3 does not i sequence all loads onto an EDG. NRC position is that we lacked understanding of the surveillance, and during discussions we ,

rejected the OSTI position. NRC questions how we hope to foster a questioning attitude among our staffif we reject a large group such as the OSTI team."

3. Attachment A of ORT-3 is titled " Test of Fmergency DC Lighting" and tests that the control room emergency DC lighting energizes when AC power is lost. ORT-3 for umt i Section 1.7 references the wrong Tech Spec section references 15.4.6-a.2, should be 15 4.6-a.3. Notified the system engineer.

4. The procedures listed under Manufacturer's Recommendations have been or will be prepared specifically to satisfy the manufacturer's recommendations. Many of the procedures are not written yet.

l 5 The NRC reviewed TS-81. 82,83 and 84 during the OSTI inspection in December,1996 The following is an excerpt from the exit meeting report. " POTENTIAL VIOLATION (TS 15 4.6.A 5): Monthly testing of the fuel oil transfer system only verifies operability of the pumps, not the entire system. We were testing the entire system annually. This is contrary to TS requirements."

l 6. TS-80 provides direction to sample the safety related dicsci fuel oil tanks. The procedure also provides the acceptance criteria for the fuel oil analysis. OI-92A provides instruction for sampling fuel oil upon receipt. Section 1.5 references the wrong Tech i Spec. It references TS-15.3.7-5,5 basis, should be 15.3.7-8 basis. Notified DSS responsible for system.

l l TS Table 15.4.12 PBF 2033 checks fuel oil in day tank and storage tank every shift.

IlX-055A/B-1/2 - G-01/02 EDG GLYCOL COOLERS Reauirements l The heat transfer characteristics of the dicsci generator glycol coolers will be monitored during functional testing. Data taken will be i SW HX outlet temperature, differential pressure, lube oil temperature and glycol temperature. The data will be trended to provide an l early indication of fouling.

pesien Basis See Requirements.

f Etsren_cs Generic Letter 89-13 PDM 92-0088

_ _.m _ _ _ _ _ . . . _ . . _ _ _ _ _ _ _ _ _ . _ _ _ _ . ._

l PBM 97-0197 March 14,1997 Page 17 Test Procedure Miscellaneous Heat Exchanger Cleaning and Inspection Program TS-81. Emergency Diesel Generator G-01 TS-82, Emergency Diesel Generator G-02 Design Basis Testina Achieved During the performance of TS-81 or 82, the parameters in Requirement 2 above are recorded on PBF-2067a or b. The forms are routed to maintenance where the data is entered into the trending program. The data is not extrapolated out to the design condition.

Worse case conditions like low flow or high lake temperature are not taken into account. Condition Report 97-0573 was initiated to address the condition.

The dicsci coolant heat exchangers are in the Miscellaneous Heat Exchanger Cleaning and Inspection Program and are scheduled for

. cleaning and inspection yearly every two years.

HX-012A/B/C/D - COMPONENT COOLING WATER HEAT EXCHANGERS Reauirements The CCW heat exchangers will be cleaned yearly with a visual inspection and an alternating year eddy current inspection schedule

. (100% tube cicaning and 20% inspection).

~ Desien Basis See Requirements.

Egference Generic Letter 89-13, Test Procedure Miscellaneous Heat Exchanger Cleaning and Inspection Program )

Desian Basis Testing Achieved 7

The component cooling water heat exchangers are in the Miscellaneous Heat Exchanger Cleaning and Inspection Program and are l scheduled for cleaning yearly and inspection es ery two years.

Z-015-PRIMARY AUXILIARY BLDG CRANE Reauirements !

All slings and special devices which will be used in st:pporting heavy loads from either the main or auxiliary hoist of the auxiliary ;

building crane shall be inspected immediately prior to use. ;

l Design Basis

- See Requirements.

i l' Reference .

TS 15.4.14

! Test Procedure l Safe Load Path and Rigging Manual SLP-4 l Desien Basis Testing Achieved SLP-4 requires form PBF 9082 to be used. The purpose of PBF-9082 is to document the inspection of the auxiliary building crane I

' lifting devices.

PBM 97-0197 l March 14,1997 Page 18 GENERIC TESTS SNUBBERS Reauirements l

1. During each refueling shutdown, a representative sample of approximately 10% of the snubbers shall be functionally tested for operability. The hydraulic snubber functional test shall verify:

a. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.

b. Snubber biced, or release rate, where required, is within the specified range in compression or tension. For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified. .

c. For each snubber found to be inoperable, an additional 10% of that type snubber shall be tested until no more failures are found or all units have been tested.

l

2. A record of senice life of each snubber, the date at which the designated scruce life commences and the installation and maintenance records on w hich the designated service life is based shall be maintained. Concurrent with the next inservice visual inspection is at least once per 18 months thereafter, the installation and maintenance records for all safety related snubbers shall be rey cwed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled prior to the next schedule service life review. If the indicated service life will be exceeded prior to the next scheduled senice life review, the snubber service life will be re-evaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond that date of the next scheduled service life review. This re-evaluation replacement or reconditioning shall be indicated in the records. ,

Desien Basis See Requirements Reference TS 15.4.13 Test Procedure Snubber Component Maintenance Program RMP-61, Hydraulic Snubber Surveillance and Testmg RMP-9060 Safety Related Snubber Visual Inspection l

l Desien Basis Testina Achieved I

1. Section 4.1 of CMP 10.1 states that approximately 10% of the Tech Spec snubbers will be tested each refueling cycle. The I' requirements are functional testing (activation, bleed or release rate, service life) and overall integrity (proper orientation, hydraulic fluid level check, proper attachment to piping and structures).

3. Section 4.1.3 of CMP 10.1 discusses a callup which requires that the component engineer reviews the history files for the 51 snubbers listed in FSAR table 6.2-13 to verify senice life has not exceeded or will not be exceeded before the next scheduled inspection.

i l

PBM 97-0197 l March 14,1997 I Page 19 ,

l PRI51ARY SYSTE31 TESTS l Epomrements

1. TS Table 15.4.1-2 Item 9a. Rod drop times of all fulllength rods

2. TS 15.3.1. A 6 and TS Table 15.4.1-2 Item 30. The pressurizer shall have 100kW of pressurizer heaters available.

Desien Basis

1. The drop times of each RCCA shall be no greater than 2.2 seconds from the loss of statici.ary gnpper coil voltage to dashpot entry (TS 15.3.10.E). ,

i

2. Pressurizer has 100 kW of heaters available (TS 15.3. l. A.6).

Beference TS 15.3.10.E i TS Table 15.4.12 Item 9a ;

TS 15.3.1.A.6 Test Procedurg RESP-3.1, PPCS Feedwater Correction Desien Basis Testine Achieved )

1. RESP 3.1 states that the rod drop times cannot exceed 2.1 seconds.

2. RESP 3.1 states to check that the energy input is greater than 100 kW.

SIODERATOR TE31PERATURE COEFFICIENT B_couirements Except during low-power physie tests, the reactor shall not be made critical when the moderator temperature coefficient is more positive than 5 pcm/F.

Reactor power shall not exceed 70% of Rated Power if the moderator temperature coefficient is positive.

Design Basis See Requirements.

Referenqs TS 15.3.1.F.1 TS 15.3.1.F.2 l

Test Procedure RESP-4.1, Test Initial Criticality and ARO Physics RESP 5.2, Reactor Engineering Tests During Escalation to Full Power Desien Basis Testing Achieved The acceptance criteria of RESP-4.1 states: " Administratively limit the Bank D withdrawal position to that determined from the temperature coefficient measurement until RCS temperature is raised to a value that is shown to lower moderator temperature coeflicient to below +5 pcm/F."

Step 5.5.6 of RESP-5.2 states: "DO not exceed 70% power level if Tm is not stable enough to ensure compliance with Tech. Spec.

15 3.1.F.2 requiring a negative MTC."

PBM 97-0197 March 14,1997 Page 20 ROD WORTil MEASUREMENT Reauirements Following each refueling shutdown prior to commencing power operation, perform rod north measurements.

Desien Basis Design worth received from Westinghouse prior to every outage as a WCAP. "The Nuclear Design and Core Management of the Point Beach Unit x Nuclear Reactor, Cycle xx."

Beference TS Table 15.4.12 Item 9b Test Procedure RESP-4.2, Control Rod Reactivity Worth Measurements Desien Basis Testing Achieved The acceptance criteria of RESP 4.2 states that the measured worth must be greater than 90% of the design worth.

REACTOR COOLANT SYSTEM TOTAL FLOW RATE Egouirements The DNB related parameters shall be maintained within the limits during Rated Power operation.

Desien Basis Urut 12181,800 gpm Umt 2 2174,000 gpm. If the Reactor Coolant System raw measured flow rate is<l74.000 gpm but 2169.500 gpm, Unit 2 shall be limited to s 98% rated power.

Reference TS 15.3.1.G 3 Basis Tgst Procedure RESP-6 2, Precision RCS Flow Rate Measurement Desien Basis Testine Achieved The acceptance criteria stated in RESP 6.2 is 2181.800 gpm for Unit I and 2174,000 gpm for Umt 2.

t

l PBM 97-0!97 !

March 14,1997 l

Page 21 REACTIVITY ANO31ALIES ,

1 Recuirements Following a normalization of the computed boron concentration as a function of burnup, the actual boron concentration of the !

coolant shall be periodically compared with the predicted value. I Qgsign Basis If the difference between the observed and predicted steady-state concentration reaches the equivalent of one percent in reactivity, an evaluation as to the cause of the discrepancy shall be made and reponed to the NRC.

Rcrerence TS 15.4.9 Tgst Procedure RESP-6.5, Reactivity Anomatics Design Basis Testing Achieved The acceptance criteria states that the normalized measured boron concentrations shall be within an equivalent of 1000 pcm l reactivity of predicted boron concentrations. 1000pcm is equivalent to one percent.

l l

l t

CONDITION REPORT CR 97-0166 STATUS: OPEN UNIT: 0 SYSTEM: VNCC INITIATED: 01/20/97 CLOSED:

MSS #: ADMINISTRATOR:

INITIATOR: ISSUE MANAGER:

NUMBER OF OPEN ACT10NS: z NUMBER OF CLOSED. ACTIONS: 0 Containment Accident Recirculation Heat Exchanger Testing No Longer Valid DESCRIPTION:

quired usin PC 56 Parts 1 and 2, " Containment Accident ThedataafonHeatExc$angerherformanceMonitoring, Recirculat Units 1 and 2" is no longer valid and is not used any more. The instruments used in the test do not have the accuracy necessr.ry to determine the heat exchanger performance.

performed to test PBTP-040, the Unit" 1 Performance Accident Fan TestCoolers.

of 1HX-15D" This was PBTP developed was and successful and will be re-written to become a routine callup.

Significance: PC-56, Parts 1 and 2 are no longer valid.

STATUS UPDATE:

i SCREENED BY : DATE: 01/21/97 l REGULATORY REPORTABLE. .. N TS VIOLATION. . :. 7.

10 CFR 21................. . N TS LCO....... (Y'N N OPERABILITY IMPACT PER TS. N JCO REQUIRED. . .

1 N

MSS REVIEW................ - N SCAQ.......... .. N OPERABILITY DETERMINATION. : N COMMITMENT. . .. N SUPPORTING DETERMINATIONS:

This, condition was not a violation of any PBNP Technical Specification and is not reportable. This CR documents that PC-56 Parts 1+2 is no longer valid and its use has been discontin(previously ued. A new questioned testing procedureunder CRwill 95-459}

be established based upon the PBTP-040 test procedure and will be applied to both Units for future testing of the containment accident recirc HXs.

l

REFERENCES:

CR 95-459 CR 96-008 PC-56, PARTS 1 & 2 PBTP-040 PC-56, PARTS 1&2 TRENDING INFORMATION:

WHEN : NON-OUTAGE

~~

l FIRST QUARTER OF 1997 l WHO : NSSS MECHANICAL SYSTEMS ENGINEERING WHY : DATA OR COMPUTATIONS WERE WRONG OR INCOMPLETE WHAT -

PROCEDURAL PROBLEM MECHANICAL HEAT EXCHANGER RELATED SYSTEM: SERVICE WATER CONTAINMENT COOLING H AND V ACTIONS PRI ACTION STATUS RESPONSIBLE PERSON DUE DATE 2 -100 ACTION NEEDED 04/25/97 e

ACTION ITEM STATUS REPORT PAGE 1 Responsible Person: _..

03/25/97

Trkid: CR 97-0166

Urgency: NO DUE DATE ASSIGNED

Action Number: 1

Work Pri6rity: 41 Activity Pending is: ACTION NEEDED

TITLE AND TASK DESCRIPTION------------------------------------------

Containment Accident Recirculation Heat Exchanger Testing No Longer Valid The data agguired using PC-56 Parts 1 and 2, " Containment Accident Recirculation HeaQ Exchanger herformance Monitoring, Units 1 and 2" is no longer valid and is not used any more. The instruments used in the test do ;

not have the accuracy necessary to determine the heat exchanger '

parformance.

performed to PBTP-040, test the Unit" 1 Performance TestCoolers.

Accident Fan of 1HX-15D" was developed and i 1

Dav91 op a new routine testing procedure for the containment accident I recirc heat 9xchangers based upon the successful testing conducted under i PBTP-040. This new test procedure should be developed for both units-and will replace PC-56, Parts 1 + 2. (PC-56 will be cancelled)

DATES-------------------------------- -----------------

Sour e Record: 01/20/97 ******* Evaluation ********* ****** Correcticn ****

Comm tment: Eval Due: Corr Act Due:

Act4on Create: 01/21/97 Action Closed:

Orig Eval Due:

Eval Done:

Orig CA Due:

Corr Act Done:

PEOPLE--------------------------------------------------------------

Responsible for Overall Action: BMS Responsible for Current Pending Activity: BMS Isgue Mana InitiaQor:ger: .. J Punch 11st Administrator: .

..._______ UPDATE--------------------------------------------------------------

(01/22/97 Receivad ace 4nn inen Group: BMS Responsible Person:

(01/22 .._) Set Work Priority to 41. Priority required based on need to do a/97test to ensure operability testing commitments of GL 89-13 for safety related heat exchangers is met.

i I

REFERENCES----------------------------------------------------------

CR 95-459 CR 96-008 PC-56, PARTS 1&2 PBTP-040

MISCELLANEOUS---------------------- --------------------------- ----

Originating Agency: S stem: VNCC NRC Open Item Number: N C Status:

Related Outages:

Engineering Work Type: None Specified Person Hours: Original Estimate =

Current Estimate =

Actual Hours =

ACTION ITEM STATUS REPORT PAGE 1

- - - - Responsible Person- ^'/25/97

Trkid: CR.97-0166

Urgency: DUE IN 31-60 DAYS

Action Number: 2

Work Priority: -100 Activity Pending is: ACTION NEEDED l j

TITLE AND TASK DESCRIPTION------------------------------------------

Containment Accident Recirculation Heat Exchanger Testing No Longer Valid The data acquired using PC-56, Parts 1 and 2, " Containment Accident Recirculation Heat Exchanger Performance Monitoring, Units 1 and 2" is no longer valid and is not used any more. The instruments used in the test do not have the accuracy necessary to determine the heat exchanger performance. PBTP-040, " Performance Test of 1HX-15D" was developed and performed to test the Unit 1 Accident Fan Coolers.

Site Engineering is developing a replacement procedure to perform this testing based upon PBTP-040. PC-56, Parts 1 and 2 need to cancelled.

DATES--------------------------------------------------------------- I Source Record: 01/20/97 ******* Evaluation ********* ****** Correction ****** '

Commitment: Eval Due: Corr Act Due: 04/25/97 Action Create:

Action Closed:

01/21/97 Orig Eval Due: Orig CA Due: 04/25/97 Eval Done: Corr Act Done-1

PEOPLE-------------------------------------------------------------- l l

Responsible for Overall Action: " '-

OPS l Responsible for Current Pending Activity: OPS :

Issue Manager: m-Initiagor: . . -

Punchlist Administrator: ----. I i

UPDATE--------------------------------------------------------------

(01/22/97 Received Action into Group: OPS Responsible eerson: Due Date: 04/25/97

)

1

REFERENCES----------------------------------------------------------

1

MISCELLANEOUS------------------------------------------------------- -

Originating Agency: System: VNCC 2 NRC Open Item Number: NRC Status: I Related Outages: {

Engineering Work Wpe: None Specified j Person Hours: Original Estimate = 1 Current Estimate = j Actual Hours =

l l

l i

i i

i I

CONDITION REPORT

. l CR 97-0548 STATUS: OPEN UNIT: 2 SYSTEM: VNCF INITIATED: 02/18/97 CLOSED:

MSS #: ADMINISTRATOR:

INITIATOR: : ISSUE MANAGER- <

NUMBER OF UPEN ACTIONS: 1 NUMBER OF CLOSED ACTIONS: U l ORT-7 Testing Method Differs Between Unit 1 And Unit 2 DESCRIPTION: l The testing method of ORT-7, Operation of Backdraft Dampers, differs between Unit i and Unit 2. THe ORT-7 for Unit 1 was revised in 1995 as a result of the evaluation of INPO SER 92-12. The procedure was revised <

to more accurately simulate fan operation during a real accident. It I was noted that the ORT-7 for Unit 2 does not contain these revisions.

ORT-7 for Unit 1 '

Also,2 Unit is classified as a major procedure.is classified as a minor procedure and ORT-7 for Significance; Unit 2 backdraft dampers are not,being tested to accurately simulate fan operation during an accident l STATUS UPDATE: !

SCREENED BY : .__ .2 DATE: 02/20/97 i REGULATORY REPORTABLE..... -

N TS VIOLATION... . ....... : N l 10 CFR 21................. : N TS LCO.................... . N l OPJ:RABILITY IMPACT PER TS. : N JCO REQUIRED.......... ... -

N MS3 REVIEW................ : N SCAQ.............. ... ..

N '

OPERABILITY DETERMINATION. : N COMMITMENT.. .. ..... ... N I SUPPORTING DETERMINATIONS:

This appears Qo be a procedural deficiency that was never revised for i one of the Units. The 50.59 perfomed for this change supports the '

revision that should have been performed. It does not appear that this has rendered any component inoperable or caused any components to be improperly, tested at this time but the Unit 2 procedure needs updating to ensure it meets ghe same req,uirements as the crocedure for Unit 1.

Therefore, no immediate operability or reportability issue exists fo:

this CR.

REFERENCES:

1 ORT-7 '

TRENDING INFORMATION:

WHEN-- : FIRST NON-OUTAGE QUARTER OF 1997 WHO : OPERATIONS '

WHY : STEPS IN PROCEDURE CONTAINED INCORRECT FACTS 1 WHAT-- : OPERATIONS PROCEDURE !

MECRANICAL FAN RELATED .

l SYSTEM: CONTAINMENT CLEANUP SYSTEM H and V ACTIONS PRI ACTION STATUS RESPONSIBLE PERSON DUE DATE

~ ~ ~

~~~~[~~~~~~[o6~~~~'hChEbh~hbbbbb~

5b235f97~ !

4 i

i l

l l

l j

I

ACTION ITEM STATUS REPORT PAGE 1

- - - - Responsible Person: . . _ _

03/25/97 i i

Trkid: CR 97-0548

Urgency: DUE IN > 180 DAYS l

Action Number: 1

Work Priority: -100

- e**************************** I Activity Pending is: ACTION NEEDED

TITLE AND TASK DESCRIPTION------------------------- -- ----

{

ORT-7 Testing Method Differs Between Unit 1 And Unit 2 Revise ORT-7 for Unit 2 to reflect the same changes made to the Unit 1 ORT-7 as a result of the evaluation of SER 92-12. In addition ensure that the classification of the Unit 2 ORT-7 is cjanged from maj,.or to minor

DATES---------------------------------------------------------------

Source Record: 02/18/97 ******* Evaluation ********* ****** Correction ****** l Commitment: Eval Due: Corr Act Due: 10/31/97 l Action Create: 02/20/97 Orig Eval Due: Orig CA Due: 10/31/97 I Action Closed: Eval Done: Corr Act Done:

PEOPLE---------------------------------------------------_---_-__---

Responsible for Overall Action: OPS i Responsible for Current Pending Activity: OPS 4 l Issue Manager-Initiator: ~

I Punchlist Administrator: i

UPDATE--------------------------------------------------------------

(03 Received Action into Grono: OPS Renp/10/97 onsible Person: Due Date: 10/31/97 i

REFERENCES----------------------------------------------------------

ORT-7

MISCELLANEOUS----------------------------------------------- - - -

Originating Agency: System: VNCF NRC Open Item Number: NRC Status:

Related Outages:

Engineering Work Type: None,Specified Person Hours: Original Estimate -

Current Estimate =

Actual Hours =

l i

1

, CONDITION REPORT CR 97-0573 STATUS: OPEN UNIT: 0 SYSTEM: VNDG INITIATED: 02/20/97 CLOSED:

MSS #: ADMINISTRATOR.

INITIATOR: _... ____ >

ISSUE MANAGER-NUMBER OF OPEN ACTIONS: 1 NUMBER OF CLOSED ACTIONS: 0 Diesel Generator Glycol Coolers Monitoring Per Generic Letter 89-13 DESCRIPTION:

In rgsponse to Generic Letter 89-13, Wisconsin Electric committed to continuall moni$or Diesel Generator Glycol Coolers during biweekly operabilit tgsting of the diesel generators. The way that this is accomplish d is Qhat data for SW Hx outlet temperature, differential pressure lube oil temperature and glvcol temperature is taken and trended.this would only detect gross aegradation. The data is not extrapolaged outto the design condition. Worse case conditions like low flow or high lake temperature are not taken into account. The coolers are cleaned and eddy current tested every two years coinciding with diesel outages.

The operability testing of the diesel generator is performed monthly.

Significance: Failure to meet NRC commitments.

STATUS UPDATE:

SCREENED BY : ..e.3 DATE: 02/21/97 REGULATORY REPORTABLE..... : N TS VIOLATION........... .. ?: N 10 CFR 21................. : N TS LCO........... ........ J.N OPERABILITY IMPACT PER TS. : N JCO REQUIRED... .......... p. N MSS REVIEW................ : N SCAQ...........

).NN OPERABILITY DETERMINATION. : N COMMITMENT. . . .. . . ..

. SUPPORTING DETERMINATIONS:

The operability of the EDG is tested monthly. The general operability of the coolers is verified monthly. This safety related equipment is considered operable. The concern is not considered reportable per our TSs.

REFERENCES:

GENERIC LETTER 89-13 VPNPD-90-027 VPNPD-092-091 TRENDING INFORMATION:

WHEN--: NON-OUTAGE 1990 - 1999 WHO :

WHi : INADEOUATE ENFORCEMENT OF ADMINISTRATIVE CONTROLS (SPAC)

WHAT -

MECHANICAL HEAT EXCHANGER RELATED CALIBRATION RELATED SYSTEM: DIESEL GENERATOR ROOM H and V This CR calls for more accurate measuring of the performance of the EDG Glycol Coolers.

ACTIONS PRI ACTION STATUS RESPONSIBLE PERSON DUE DATE

~ ~ ~ ~ [ ~ ~ ~ ~ ~ ~ [ 6 6 ~ ~ ~ ~ ~ UT E UU ' UE E bE b ' .' ' .' '. ' ~. .~ .~ .~ ~ ~. ~. ~ .~

ACTION ITEM STATUS REPORT PAGE 1 eo***************ve************ Responsible Person: 03/25/97

- Trk$d: CR 97-05"/3 Urgency: NO DUE DATE ASSIGNED I Action Nuder: 1 Work Priority: -100 see**************************** ,

Activity Pending is: ACTION NEEDED

TITLE AND TASK DESCRIPTION------------------------------------------

Diesel Generator Glycol Coolers Monitoring Per Generic Letter 89-13 Notify the NRC of the frequency change of monitoring the Diesel Generator Glycol Coolers. Purchase the equipment / services to accurately monitor the performance of the coolers.

DATES----------------------------------------------------

Sour e Record: 02/20/97 Comm tment:

- - - - Evaluation ********* ****** Correct -

a a a

Eval Due: Corr Act Due:

Action Create: 02/21/97 Action Closed:

Orig Eval Due: Orig CA Due:

Eval Done: Corr Act Done

PEOPLE--------------------------------------------------------- - -

Responsible for Overall Actign: BMS l Recponsible for Current Pending Activity: BMS !

Icsue Manager: '

1 Initia$or:

Punchlist Administrator:

---.------UPDATE-------------------------------------------------------------- !

(02/24/97 . Received Action into Group: BMS Ronponsible Person:

REFERENCES----------------------------------------------------------

GENERIC LETTER 89-13 VPNPD-90-027 VPNPD-092-091

MISCELLANEOUS- -------------------- --------------------------------

Originating Agency: S stem: VNDG NRC Open Item Number: N C Status:

Related Outages:

- Engineering work Type: None,Specified Person Hours: Original Estimate =

Current Estimate =

Actual Hours =

o-CONDITION REPORT CR 97-0574 STATUS: OPEN UNIT: O SYSTEM: VNBI INITIATED: 02/20/97 CLOSED:

MSS #: ADMINISTRATOR:

ZNITIATOR: - _.... 3 ISSUE MANAGER-Nh BER OF OPEN ACTIONS: 1 NUMBER OF CLOSED ACTIONS: O PAB Battery Room Coolers Monitoring Per Generic Letter 89-13 DESCRIPTI N:

Descr ptionIn response to Generic Letter 89-13, Wisconsin Electric comm ted to continually moniQor the PAB Battery Room Vent Coolers HX 105A B. The accuracy of the instruments to monitor performance of,HX-105ABisnotkubeand$inmaterialcannotood invo ved. The enou heformodeled the small temberatures accurately in the differences !

analysis software so approximations must be used. The testina method has been-changed to periodic cleaning and eddy current examin& tion wh..n meets the intent of Generic Letter 89 13.

// Significance: Failure to meet NRC commitment.

STATUS UPDATE:

SCREENED BY : DON PETERSON DATE: 02/21/97 REGULATORY REPORTABLE..... . N TS VIOLATION...... ....... .N 10 CFR 21................. : N TS LCO......... ........ : N OPERABILITY IMPACT PER TS. : N JCO REQUIRED.. ........... : N MSS REVIEW................ : N SCAQ.................. ... : N OPERABILITY DETERMINATION. : N COINITMENT................ : N SUPPORTING DETERMINATIONS:

The testing method has been changed to periodic cleaning and eddy current examination, this meets the intent of the GL 89-13. The CR address the concern to more accurately measure the effectiveness of the Heat Exchanger. The change in measuring technique did not affect the operability of any saf 9ty related equipment, A chance to update this commitment is not considered to be a violation of the previous commitment.

REFERENCES:

I GENERIC LETTER 89-13 RESPONSE TO GENERIC LETTER 89- '

13, VPNPD-90-027 TRENDING INFORMATION:

WHEN--: NON-OUTAGE 1990 - 1999 WHO :

WHY : INADEQUATE ENFORCEMENT OF ADMINISTRATIVE CONTROLS (SPAC)

WHAT --

-MEC ICAL HEAT EXCHANGER RELATED TOOLS TEST EQUIPMENT RELATED SYSTEM: PAB B TTERY and INVERTER ROOM H and V A more accurate measurement of heat exchanger performance is being requested. l To run a test when the lake temperature is 40-50 degrees compared to a possible l 75 degree lake temp would at present give different outcomes. At present we ;

are measuring the in and outs not the direct heat transfer / efficiency of the Heat exchanger.

ACTIONS PRI ACTION STATUS RESPONSIBLE PERSON DUE DATE I

~~~~{~~~~~_~ico~~~~~ibT5bb hbbbbb_'_'_'_ _~~~~~~~~~ ~~~~~~~~~~~~~ ~ '

, ACTION ITEM STATUS REPORT PAGr '

i

- - - - Responsible Person: 03/25/;~7

Trkid: CR 97-0574

Urgency: NO DUE DATE ASSIGNED

Action Number: 1

Work Priority: -100 Activity Pending is: ACTION NEEDED

TITLE AND TASK DESCRIPTION------------------------------------------

PAB Battery Room Coolers Monitoring Per Generic Letter 89-13 Purchase the equipment / services to accurately monitor the performance of the coolers or notify the NRC of the change in PAB Battery Room Coolers testing method.

DATES---------------------------------------------------------------

Sour e Record: 02/20/97 Comm tment:

- - - - Evaluation ********* ****** Correction ******

Eval Due: Corr Act Due:

ActLon Create: 02/21/97 Orig Eval Due: Orig CA Due: :

ActLon Closed: Eval Done: Corr Act Done: '

PEOPLE--------------------------------------------------------------

Responsible for Overall Action: BMS Responsible for Current Pending Activity: BMS !

Iasue Manager:

Initiator:

Punchlist Administrator: .

1

UPDATE-------------------------------------------------------------- j (02/24/97 F" . Received Action inrn Group: BMS ,

Responsible Person:

j 1

l

REFERENCES----------------------------------------------------------

MISCELLANEOUS---------------------- -------------------------------- l Originating Agency: S stem: VNBI NRC Open Item Number: N C Status:

Related Outages:

Engineering Work Type: None Specified Person Hours: Original Estimate =

Current Estimate =

Actual Hours =

I 1

- . . . . . - . . .-..- . - . . . . ~ . - - - . . . _ - - . . - . . . .-- --_- -

POINT BEACH UNIT 2 COMMITMENT i INDEPENDENT REVIEW RESULTS l Commitment ID Number 12 l I

- Commitment Description ' !

P Review 20% of the surveillance procedures associated with safety significant non-pump and valve !

components (such as heat exchangers and fans) to ensure that the surveillance acceptance criteria !

satisfy the requirements of the plant design basis / accident analysis. Make changes as necessary as i a result of this review. '

r This commitinent is also Enforcement Conference Commitment # 47 Review Methodology identify the population of surveillance procedures associated with safety significant non-pump and i non-valve components. ,

l t

Verify that at least 20% have been selected and reviewed and that the selection process was not !

biased in a non-conservative manner. Note that PBNP staff already performed 100% review. This ;

{

>; _ was not known at the time of development of this methodology. !

g)

Verify that the acceptance criteria for those reviewed satisfy the requirements of the plant design basis / accident analysis.' ;

As necessary, expand the review sample by 10% to provide additional assurance that this [

population of surveilbnce procedures adequately reflect the accident analysis / design basis in their acceptance criteria. Not: that PBNP staff already performed 100% review. This was not known at !

the time of developmen; of this methodology, !

1 Review Results l l

From discussions with the responsible person and as evidenced by the work performed to date on this commitment, safety significant non-pump and valve components were reviewed to ensure that their surveillance acceptance criteria satisfy the requirements of the plant design basis! accident analysis. The PBNP staff approach for this review was to take a list of safety related components generated from the Champs data base and compare it to a list of surveillance procedures.

Calibration, Mectrical, sampling or chemistry procedures were not part of this review. The non-pump and non-valve component surveillance procedures identified by this comparison was then the list of procedures to review for the proper acceptance criteria. While at first a 20% sample review was initiated, it was expanded by the PBNP staff to a 100% review of the identified surveillance procedures.

e Page 1 of 4-

POINT BEACH UNIT 2 COMMITMENT i INDEPENDENT REVIEW RESULTS l

Commitment ID Number 12 j l

The listing of the procedures reviewed by the PBNP staff are as follows:

PBNP Common CMP-10.1 Snubber component Maintenance Program HPIP 11.54 Control Room, F-16, Filter Testing IT-11A Performance Test fur Spent Fuel Pool Heat Exchanger, HX-13A/B IT- 560 Leakage Reduction and Preventive Maintenance Program Test of Chemical and Volume Control System Holdup Tanks (Refueling)

IT- 570 Leakage Reduction and Preventive Maintenance Program Test of Drain System PC-56 Part 4 HX-105B Performance Test Battery Room Cooler PC-56 Part 5 HX-105B Performance Test Battery Room Coolers Analysis l

Form PBF-2033, Turbine Building Shift Log, Unit 2 RMP-37 Diesel Fire Pump Engine Inspection RMP-57 Fire Barrier Penetration Fire Seal Surveillance RMP-58 Containment Fire Seal and Conduit Wrapping Inspection, Unit 1 RMP-59 Containment Fire Seal and Conduit Wrapping Inspection, Unit 2 RMP-61 Hydraulic Snubber Surveillance and Testing RMP-63 Low Pressure Turbine Rotor Testing -

RMP-9060 Safety R. elated Snubber Visual Inspection RMP-9094 Diesel Fire Pump Batten Surveillance TS-09 Control Room Heating and Ventilation Monthly Checks TS-32 Safety Valve Position Verification Subcooling Margin Computing System-Contamment Purge Valve Position TS-70 Monthly Diesel Engine-Driven Fire Pump Functional Test TS-71 Monthly Electric Motor-Driven Fire Pump Functiona' Test TS-72 Annual Fire Pump Capacity Test TS-73 Monthly Fire Protection Control Valve Position Verification TS-74 Annual Underground Fire Main Flow Test TS-75 Biennial Service Testing of Fire Hose and Fire Hose Stations TS-76 Quarterly Automatic Sprinkler and Water Spray System Surveillance Test TS-77 Semi-Annual Smoke Detection System Integrity Test TS-78 Semi-Annual Halon 1301 Fire Suppression System surveillance Test TS-79 Monthly Surveillance of Fire Hose Stations TS-80 Sampling of Emergency Fuel Oil Tank, Fuel Oil Storage Tanks and EDG Day Tanks TS-81 Emergency Diesel Generator G-01 Monthly TS-82 Emergency Diesel Generator G-02 Monthly TS-83 Emergency Diesel Generator G-03 Monthly TS-84 Emergency Diesel Generator G-04 Monthly

OI-92A Fuel Oil Ordering, Receipt, Sampling and T-173 Fill Tank Draining RMP 9043 Series, Diesel Generator Preventative Maintenance Procedures

( Form PBF 2031, Auxiliary Building Shift Log Page 2 of 4

4 A

g POINT BEACH UNIT 2 COMMITMENT s,

INDEPENDENT REVIEW RESULTS i

Commitment ID Number 12 )

3 Form PBF-2033, Turbine Building Shift Log, Unit 2 Safe Lead Path and Rigging Manual, SLP-4 Miscellaneous Heat Exchanger Cleaning and Inspection Program l

GENERIC EPIP-10.3 Post Accident Containment Ventilation System Operation RESP 3.1 PPCS Feedwater Correction RESP 4.1 Initial Criticality and ARO Physics Test RESP 4.2 - Control Rod Reactivity Worth Measurements RESP 6.2 Precision RCS Flow Rate Measurement RESP 6.5 Reactivity Anomalies PBNP Unit 1 ORT-3 Safety Injection Actuation with Loss of Engineered Safeguards AC, Unit 1 ORT-7 Operation of Backdraft Dampers, Unit I l ORT-61 Sump A Drain to Auxiliary Building Drain, Unit I ;

PBTP-040 Performance Test of 1HX-15D, Containment Fan Cooler '

PC-56 Part 1 Containment Accident Recire Heat Exchanger Hanger Performance Monitoring Test-Ul TS-33 Surveillance Testing, Containment Accident Recire Fan Cooler Units (monthly) :

UI TS-37 Surveillance Testing: Containment Accident Recire Fan-Cooler Units U-l PC-09 Part 2 Unit 1 Safeguard Systems Valve and Lock Checklist (Monthly)

PBNP Unit 2 ORT 3 Safety injection Actuation with Loss of Engineered Safeguards AC, Unit 2 ORT-7 Operation of Backdraft Dampers, Unit 2 ORT-61 Containment Sump A Drain, Unit 2 PC-56 Part 2 Containment Accident Recire Heat Exchanger Performance Monitoring Test-U-2 TS-34 Surveillance Testing: Containment Accident Recire Fan-Cooler Units- U2 TS-38 Contair. ment Spray Nozzles Check, Unit 2 PC-9 Part 3 Unit 2 Safeguard Systems Valve and Lock Checklist (monthly)

* *

Others Procedures as identified in memo PBM 97-0197, dated 3/14/97, " RESTART COMMITMENT 12 REPORT" Page 3 of 4

- + --e1 W

m .- . _ ~ . _ - - . - - . _ - _ . _ , _ . . _ _ _ . _ _ _ . _ _ _ _ _._ ____._

r POINT BEACH UNIT 2 COMMITMENT INDEPENDENT REVIEW RESULTS ,

i Commitment ID Number 12 !

l l

l It is recognized that some of the above procedures include fire service pump and valve .ating,

{

which was not part of this commitment but were included because the responsible person believed

! they needed review since they are not part of the IST Program.

l l This reviewer read through the procedure indexes for Operations Refueling Tests (ORT's) '

I Technical Surveillance Tests (TS's), Periodic Checks (PC's), inservice Tests (IT's), and Reactor !

) Engineering Surveillance Procedures (RESP's). While some procedure titles caused concem that ;

j they may be in scope for this commitment, review of the procedure and discussions with the *

! responsible person resolved these concerns.

6 Of the above listing ofin-scope procedures, the following procedures were independently reviewed .'

and found to have acceptance criteria that supported the PBNP design basis / accident analysis: l TS-33 TS-34, TS-09, RESP-4.1, RESP-3.2, RESP 4.2, and RESP 6.2. i l

i l

Recommendations -

,' Based on this independent review there are no items associated with this Commitment # 12 which

~

V would impede Unit 2 Restart. 'i l .i t

As a program enhancement, it is recommended that the PBNP staff evaluate the need to !

periodically verify that the Residual Heat Removal Heat Exchangers (2HX-11A/B) can perform at !

L . its design heat duty of 24.15 E6 BTU /HR (FSAR Tr.ble 6.2-7). !

L !

t i

l I

I

\

i f

- Reviewed by:1 -

l l

L Page 4 of 4 l

POINT BEACH NUCLEAR PLANT UNIT 2 STARTUP COMMITMENT LIST '

i April 7,1997 Status Update IDENTIFICATION AND RESOLUTION OF ISSUES PERTINENT TO REACTOR SAFETY The following actions will be taken prior to Unit 2 criticality, except as specifically noted. The scope of reviews will be examining the identified documents or items for accuracy and compliance with requirements. Should any reviews identify either generic issues or significant discrepancies which could negatively impact reactor safety, the scope of those reviews will be expanded. Where discrepancies are identified, appropriate corrective and preventive actions will be taken commensurate with their safety significance.

Ccamitment Description . Status ID Number Complete a detailed Unit 2 Containment Materiel Condition Assessment, addressing in progress.

I housekeeping, system walkdowns, materiel condition, and instrumentation. Extensive work inside Containment was conducted this outage due to the Steam Generator replacement project.

2 Walkdown all accessible Unit 2 and common Maintenance Rule systems for adequate visual in progress.

material condition.

Walkdown all accessible Unit 2 and common systems for outstanding work order tags. All work and verification 3 Note: The scope was expanded to include all accessible Unit I systems. completed. Documentation sent to NRC.

Conduct as-built inspections of the electrical and I&C components on the Unit 2 CVCS and CCW All work and verification 4 systems (Work Orders 9607322,9611140,9606548, and 9611139). completed. Documentation sent to NRC.

Complete Work Orders 9513222 through 9513225 to conduct inspections of Appendix R attemate All work and verification 5 power transfer switches. completed. Documentation sent to NRC.

Complete Work Order 9604151 to perform foreign material exclusion inspections on the Unit 2 All work and verification 6 4160V safeguards bus 2A-06 and breakers. completed. Documentation sent to NRC.

Complete a review of Unit 2 administrative controls implementing or referencing Technical All work and verification 7 Specifications to ensure Technical Specification requirements are appropriately reflected in the completed. Documentation administrative controls. sent to NRC.

Pagei

Review 20% of the Operations Technical Specification, Inservice Test, and Operations Refueling In progress.

Test related surveillance procedures, with concentration on those ir.volving major equipment. '

8 Upgrade as necessary to include appropriate initial conditions, retnrn to service lineups, properly specified independent verification, reviewing acceptance criteria, and Technical Specification implementation.

Review the In Service Testing (IST) acceptance criteria for the remaining IST pumps to ensure All work and verification 9 that the IST acceptance criteria meets the design basis / accident analysis requirements. Make any completed. Documentation sent to NRC.

changes necessary gs a result of this review.

Review the In Service Testing acceptance criteria for all IST valves to ensure that the IST All work and verification 10 acceptance criteria meets the design basis / accident analysis requirements. Complete necessary completed. Documentation operability evaluations, revise procedures, and resolve Unit 2 equipmeat discrepancies. sent to NRC.

Complete the following regarding installed instrumentation used in the IST program: All work and verification completed. Documentation

. Identify the Unit 2 installed instruments used in the IST program. sent to NRC.

. Review the performance of the identified instruments over the last 3 years.

I1 . Review the suitability of the instrumentation for use in the IST program.

. Review all IST pump hydraulic data over the past year for adverse trends.

As necessary, make changes as a result of these actions.

Review 20% of the surveillance procedures associated with safety significant non-pump and valve All work and verification components (such as heat exchangers and fans) to ensure that the surveillance acceptance criteria completed. Documentation in 12 satisfy the requirements of the plant design basis / accident analysis. Make changes as necessary as route to NRC. ,

a result of this review.

Note: This has been expanded to a 100% review. ,

13 Review other operating procedures that contain maintenance activities and revise as necessary to In closeout verification ensure PMT and QC are properly addressed by those procedures. process.

Review equipment return to service testing requirements prior to the following U2R22 mode Will occur approximately one 14 change readiness reviews to ensure the required equipment is operable prior to changing modes: week prior to each of the core reload, leaving cold shutdown, and the approach to criticality. mode changes.

All ,vork and verification Review 20% of the work orders performed since January 1,1995 on Unit 2 or common PSA safety 15 significant systems (AFW, SW, EDG, I A,4.16 kv, gas turbine, and CCW) to verify adequate PMT completed. Documentation was performed to ensure system / component safety function. sent to NRC.

Complete all Unit 2 Maintenance Rule related work order post-work, pre-PMT reviews prior to the All work and verification 16 approach to criticality. completed. Documentation sent to NRC.

Page 2

-_ . - -=- . - .- .- . _. . -, -.

17 Review 50.59 screenings conducted in 1996. Upgrade those determined to require a 50.59 Review completed. i 1

evaluation. Upgrading in progress. .!'

I8 Review outstanding JCO's. Perform operability determinations and 50.59 evaluations needed to In progress.

address the issues. j Conduct a review of 50.59 evaluations from this outage. Ensure all conditions of the evaluations Initial review completed. .

have been co npleted. Reviews of emergent 50.59 19 evaluations in progress. t Tricking completion of '

~

' ~ ~

conditions through the outage. l 20 Review items from existing open item lists (e.g., NUTRK) to identify potentially degraded in progress. j equipment.

21 Review open items from the Design Basis Document development program. In progress.

All open operability evaluations for Unit 2 and common equipment will be reviewed for In progress. This will 22 acceptable closure of the degraded equipment issue. Disposition outstanding issues in accordance continue through the outage.

with 10CFR50.59 and Generic Letter 91-18.

Review 20% of the Condition Reports closed since January 1,1995 which are associated with In closcout verification 23 PSA safety significant systems for degraded equipment operability issues to ensure that we have process. ;

adequately identified and dispositioned operability issues.

This has been expanded to a 100% review of PSA safety significant systems.

Complete an additional Outage Safety Review for the startup phase of the outage. In progress.

24 i i

Conduct an integrated review of all outage licensing commitments (50.59's, enforcement In progress.

25 conference items, Technical Specification Change. Requests, and Reload Safety Analysis). Ensure all requirements are met.

Revise ORT-3 and DCS 3.1.11 to ensure Technical Specification 15.44.A.2 testing includes All work and verification i 26 dynamic loading of the EDG with sequenced loads. completed. Documentation ,

sent to NRC. -

Test all EDGs in accordance with revised ORT-3 and DCS-3.1.11. Retum the electrical systems Re-opened. QA will be 27 to normal alignment prior to leaving cold shutdown. reviewing the ORT-3 documentation.

Resolve the containment penetration commitments, including: In progress.

28 '

. CP-32 (Containment penetration for Auxiliary Charging line).

. Penetration thermal reliefissue.

Page 3

Complete a 50.59 evaluation for the existing CCW supply to the RCP seals as a safety function. Re-opened. Does not appear 29 that a 50.59 is an appropriate -

vehicle to do this.

Considering alternatives.

30 Update the diesel generator loading calculation N-91-016 to properly reflect the loading of the In progress.

Containment Fan Coolers.

31 Evaluate the adequacy of coordination on the 120 VAC instrument bus system through a 50.59 or In progress.

operability review.

Implement interim improvements for the Condition Reporting process, based on a review of In progress.

32 assessments and identified recommendations for improving that process.

Implement intedm improvements for the 50.59 process to require that all screenings be either All work and verification 33 authored or reviewed by a member of the multi-disciplinary review team. completed. Documentation sent to NRC.

34 Upgrade Unit 2 operations checklists to include requirements for initials, time, and date. During Re-openei the review, verify that the checklists are technically correct.

Revise applicable IST program documents to prevent equipment from being retumed to service All work and verification (declared operable) with vibrations in the alert range. completed. Documentation 35 sent to NRC.

Revise NP 8.1.1, Work Order Processing, and NP 8.1.3, Post-Maintenance Testing to ensure post- Re-opened.

36 maintenance testing , operability testing, and surveillance test requirements are properly addressed.

Include return to service testing in the plant schedule, both outage and nonoutage. All work and verification 37 completed. Documentation sent to NRC.

Page 4

COMPLETE PHYSICAL WORK WHICH SUPPORTS SAFE STARTUP AND POWER OPERATIONS Modifications which Point Beach Nuclear Plant has identified as being significant to safety and scheduled for completion in U2R22 will be in an accepted status (i.e., the applicable physical work completed, post-maintenance testing completed satisfactorily, and the associated component / system being declared operable) prior to being required to be operable per Technical Specifications. These modifications are:

Cemmitment Description Status ID Nu'mber 38 Modification 96-033 - replace control power transformers on Motor Control Centers 2B32 and in progress. One remains to 2B42. be installed.

Modification 90-048 - replace Boric Acid and Reactor Makeup Water totalizers, replace the Awaiting PMT.

39 CVCS control switch, replace flow indicators, and refurbish flow controllers. This resolves an Operator workaround issue.

40 Modification 94-097 - remove six RCS loop drain valves. Awaiting PMT.

Modification 92-141 - relocate the RhIR flow control valve controllers on 2CO3 for human All work and verification 41 factoring. completed. Documentation sent to NRC.

Modification 96-073 - seismically upgrade CCW, SI, RIIR, and RIIR/ letdown piping supports All work and verification 42 and remove an AFW snubber. completed. Documentation sent to NRC.

Modification 94-066 - install a soft seat in containment isolation valve 2SI-834D, and add a In closcout verification 43 relief valve and pressure regulator in the nitrogen supply line to the Si accumulators. This process.

resolves an Operator workaround issue.

44 Modification 96-065B - seismically upgrade the Refueling Water Storage Tank recirculation In closeout verification line. process.

Modification 96-054 - install pressure gauges in the service water retum header from the On hold. Waiting for plant 45 Emergency Diesel Generator GOl and GO2 glycol coolers, and reset the throttle valves in that condition changes.

line.

Modification 96-022 - install a new 125 VDC feed to 480V safeguards bus 2B03. All work and verification 46 completed. Documentation sent to NRC.

Modification 94-055 - add seismic supports to the raceway between risers 56 and 62 on C04 All work and verification 47 (Reactor and Primary Plant Control Board). completed. Documentation sent to NRC.

Page5

48 Modification 96-068B - eliminate containment heating steam and condensate return In progress. -

containment isolation valves. .

49 Modification 96-053 - replace an elbow in the svest service water header. In progress.

50 Modification 95-070 - seismically upgrade the containment cooling fans and filters. In closecut verification process.

Modification 96-026 - install, delete, and modify supports for feedwater, main steam, and SI All work and verificati~2 51 system piping for the 79-14 project. completed. Documentation

~

sent to NRC.

Modification 96-058 - move Power Plant Computer System alarms to the exterior of C-20 All work and verification 52 panels. completed. Documentation sent to NRC.

Modification 94-095 - replace 8 Main Steam Condenser steam dump valves with improved Awaiting PMT (PMT will be 53 design. completed following reactor

. startup).

54 Modification 95-029 - replace Si accumulator level transmitters. Awaiting PMT.

55 Modification 95-035 - modify Containment Spray additive tank controller circuit. In closeout verification process.

Modification 96-063 - replace 345 KV breakers (3-4,4-5, and 142). Awaiting PMT (PMT will not 56 be completed until Unit 2 is on-line).

57 Modification 96-069 - replace four breakers (1 Y-06-01,1 Y-06-03,1 Y-06-05, and 1 Y-06-11) In closecut verification associated with instrument bus 1 Y-06. process.

Modification 95-058'O - repair Steam Generator intermediate leg supports. This may be Awaiting PMT (will not be 58 resolved through analysis. completed until the unit is heated-up).

59 Modification 96-070 - replace molded case circuit breakers associated with instrument buses in closeout verification 2Y-05 and 2Y-06. process.

Page 6

The work and testing associated with these Work Orders will be completed prior to the associated component / system being declared operable.

Emergent Work Orders associated with Maintenance Rule Risk Significant Systems which Point Beach Nuclear Plant defines as priority level 1 to 4 , j will be completed prior to Unit 2 criticality. i Cammitment . Description Status ID Number Work Orders 9601506, %02502, %03921,9611267, %11278, and %11755 - replace in closeout verification '

60 proximity switches a'nd targets with an im' proved design and overhaul the Fuel Transfer Cart ' process.

to enhance control system operation. This resolves an Operator workaround issue. ;

Work Orders 9613568 and 9613569 - provide bonnet pressure locking relief for the SI-857A Work complete. PMT

61 and SI-857B valves (interface valves between RilR and Iligh Head SI) on Unit 2. scheduled for week of April 7, 1997.

62 Work Order 9611757 - correct the leakage which leads to boric acid buildup in the cylinder Awaiting PMT.

blocks of"B" Charging Pump. !

63 Work Order %03532 - repair the handswitch for 2P-2A, the "A" Charging Pump. Awaiting PMT. 'J 64 Work Orders 9611624 through %11626 - replace existing pneumatic turbine generator Work is scheduled. -l circuitry time delay relays with plug-in, electmnic time delay relays. !

Work Order 9606626 - reinstall switches on the Unit 2 Containment hatch third door to allow All work and verification -

65 monitoring of door status. completed. Documentation sent to NRC. :

Work Order 9611052 - replace the 2P-10B switch, the "B" RIIR Pump control switch. All work and verification 66 completed. Documentation ;

sent to NRC.

67 Work Orders 9611198 and 9611199 - repair the body-to-bonnet boric acid leak on CV-307 B Awaiting PMT.

(lowside tap for "B" RCP #1 seal d/p) and CV-308B (lap seal d/p for "B" RCP). ,

t I

i Page 7 t i

+

.....m. ._ - . __ -. _ __-_.___m_

_ _ _ _ _ _ ____.____.._________m.__m._mm___-ma_____._______ _____.__1___ _ _ _ _ . _ _ _ . _ _ _

The following actions will be completed to correct Operator workarounds prior to Unit 2 criticality, except as specifically noted:

Description Status Commitment ID Number Repair valve AR-3511 per Work Order 9513340. The Unit 2 priming air ejector is blank Awaiting PMT.

68 flanged due to air in-leakage through the condenser air removal isolation valve, AR-3511.

Repair the drain valve for the heating steam moisture separator per Work Order 9613451. The Work is scheduled.

69 Unit 2' heating steam moisture separator level has'been difficult to mairitain during normal ~

operations, and frequent alarms were received due to low level. This will be tested following Unit 2 startup.

Install a new level control system for the brine tank (T-118) per Modification 92-008*Q. The All work and verification tank overflows because the installed automatic level control system is not effective, and there completed. Documentation 70 is no high level alarm for the tank. sent to NRC.

Repair MS-249, the Unit 2 steam line sample valve, per Work Order 9603128. The valve had Awaiting PMT.

71 a packing leak which required steam header sampling to be shifted to the B steam header.

Repair alarm switch 2LS-2511 per Work Order 9605711. The Unit 2 D MSR level was being Awaiting PMT.

72 maintained low in the band due to level oscillations and a steam leak from the alarm switch.

Repair 2P116, the Unit 2 Boric Acid Recirculation Pump, per Work Order 9603130. It has a Work is scheduled.

73 significant seat leak.

PERSONNEL AND LICENSING READINESS The following actions will be completed prior to Unit 2 criticality:

Description Status Commitment ID Number Each operating crew will receive simulator training to gain proficiency in casualty response, All work and verification the expected response of the newly installed steam generators and reactor core, and placing the completed. Documentation 74 sent to NRC.

turbine on-line.

Revise the initial and requalification operator training plans to include a review of the Re-opened. Need to better administrative procedures identified as significant to daily operation of the plant during each define the administrative 75 two year operations training plan. controls.

Page 8

Conduct roundtable discussions with all MSS \SS\DTA personnel regarding conservative In progress. Three people -

76 decisionmaking, Technical Specification interpretations, and lessons teamed from recent remain to receive the training. ,

regulatory communications and perspectives. Review outlier Technical Specification in:erpretations for interim applications.

77 Complete the procedure changes and training associated with the new Technical Specification In progress.

on ECCS regarding the new Containment Integrity Analysis.

78 Communicate specific expectations regarding AFW and EDG status control to Operators. In progress.

79 Restor'e a proceduralized capability to operate the' Containment Spray Pumps in the In progress.

recirculation mode of the ECCS.

Obtain amendments requested by Change Requests 188 and 189 related to Steam Generator In progress.

replacement; 192 related to Service Water operability; and 194 related to Low Temperature Overpressurization limits. This will include resolution ofissues related to Control Room and 80 offsite dose evaluations for the analyzed events.

Submit the following requests for license amendments resulting from the review of existing In progress.

Technical Specification interpretations:

Revise the maximum acceptable power level when crossover steam dumps are inoperable (TS 15.3.4.E).

81 . Revise requirements for offsite power lines availability to address adequacy (TS 15.3.7.A.I .a).

Remove allowances in TS 15.3.1.A.l.a for, single reactor coolant pump operation.

. Appropriately modify the minimum required boron concentration in the Refueling Water Storage Tanks.

i Status Exolanation:

In closeout verification process - work and PMT, as applicable, have been reported as complete. The independent review by Duke Engineering is either in progress or issues from that review are being addressed.

Page 9

.e - -

PBNP UNIT 2 CORE LOAD ISSUES -

As of April 7,1997 ,

BOLDED INDICATES READY FOR CORE LOADING.

I

~

Where discrepancies are identified during co'nduct of each of these commitments, appropriate corrective and preventive actions will be taken prior to core load commensurate with their safety significance. j ID # Description What Must Be Done Work Status Independent Prior to Core Load Verification Status Complete a detailed Unit 2 Containment Materiel Condition Complete the assessment In progress. Draft independent 1 Assessment, addressing housekeeping, system walkdowns, materiel for systems and -

verification supports condition, and instrumentation. Extensive work inside Containment was components needed for core load. ;

conducted this outage due to the Steam Generator replacement project. core load. ,

Walkhwn all accessible Unit 2 and common Maintenance Rule systems Complete the walkdown In progress. Independent 2 for adequate visual material condition. of those systems and verification drafted.

components needed for core load.

Walkdown all accessible Unit 2 and common systems for Complete walkdowns COMPLETE. FINAL outstanding work order tags. for those systems and INDEPENDENT 3 Note: The scope was expanded to include all accessible Unit 1 components needed for VERIFICATION systems. ,

core load. SUPPORTS CORE LOAD.

Complete Work Order %04151 to perform foreign material Complete prior to core COMPLETE. FINAL exclusion inspections on the Unit 2 4160V safeguards bus 2A-06 and load. INDEPENDENT 6 breakers. VERIFICATION ,

SUPPORTS CORE LOAD. !

Complete a review of Unit 2 administrative controls implementing Complete the review of COMPLETE FINAL ,

or referencing Technical Specifications to ensure Technical Refueling Procedures INDEPENDENT !

7 Specification requirements are appropriately reflected in the RP-1 A and RP-1B, and VERIFICATION administrative controls. Technical Specification SUPPORTS CORE i Section 15.3.8. LOAD.

Page1 l

I

Review th2 la Servica Testi:g (IST) cecept=ce criteria f:r the Complet2 the review COMPLETE. FINAL -

remaining IST pumps to ensure that the IST seceptance criteria for those IST pumps INDEPENDENT ,

.9 meets the design basis / accident analysis requirements. Make any needed to support core VERIFICATION changes necessary as a result of this review. load. SUPPORTS CORE ,

LOAD.

Review the In Service Testing acceptance criteria for all IST valves Complete the review COMPLETE. FINAL I to ensure that the IST acceptan'ce criteria meets the' design for those IST valves INDEPENDENT-10 basis / accident analysis requirements. Complete necessary needed to support core VERIFICATION operability evaluations, revise procedures, and resolve Unit 2 load. SUPPORTS CORE ,

equipment discrepancies. LOAD. <

Complete the following regarding installed instrumentation used in Complete for IST COMPLETE. FINAL the IST program: program INDEPENDENT >

instrumentation needed VERIFICATION e Identify the Unit 2 installed instruments used in the IST to support core load. SUPPORTS CORE program. LOAD.

11 e Review the performance of the identified instruments over the last 3 years.

Review the suitability of the instrumentation for use in the IST ,

program.

Review all IST pump hydraulic data over the past year for adverse trends.

As necessary, make changes as a result of these actions.

Review 20% of the surveillance procedures associated wi_th safety Complete the review COMPLETE. FINAL significant non-pump and valve components (such as heat for those surveillance INDEPENDENT 12 exchangers and fans) to ensure that the surveillance acceptance procedures needed to VERIFICATION criteria satisfy the requirements of the plant design basis / accident support core load (TS- SUPPORTS CORE analysis. Make changes as necessary as a result of this review. 09 and IIPIP 11.54). LOAD. j Note: This has been expanded to a 100% review.

Review other operating procedures that contain maintenance activities Complete the review for in progress. Draft independent and revise as necessary to ensure PMT and QC are properly addressed those operating verification supports by those procedures, procedures needed to core load.

13 support core load.

Page 2

Review equipment return to service testing requirements prior to the Complete a Readiness Will be Independent -

following U2R22 mode change readiness reviews to ensure the required Review prior to core conducted verification drafted. ,

14 equipment is operable prior to changing modes: core reload, leaving load. approximately ,

cold shutdown, and the approach to criticality. one week prior j to core load.

Review 20% of the work orders performed since January 1,1995 on Complete the review COMPLETE. FINAL Unit 2 or common PSA safety significant systems (AFW, SW, EDG, for those INDEPENDENT '

15 IA,4.16 kv, gas turbine, and CCW) to verify adequate PMT was - systems / components VERIFICATION performed to ensure system / component safety function. needed to support core SUPPORTS CORE load. LOAD. !

Review 50.59 screenings conducted in 1996. Upgrade those determined Complete the review. Review Independent ;

to require a 50.59 evaluation. Prior to core load, reported verification drafted. !

upgrade those screenings complete.

17 needed to support core, Four upgrades load. need to be !

I done prior to i core load. i Conduct a review of 50.59 evaluations from this outage. Ensure all Complete the review. In progress. Draft independent conditions of the evaluations have been completed. Ensure conditions needed verification supports 19 to support core load are core load. l completed prior to core [

loading.

20 Review items from existing open item lists (e.g., NUTRK) to identify Complete the review In progress. Independent potentially degraded equipment. prior to core load. verification drafted. !

All open operability evaluations for Unit 2 and common equipment will Complete the review for In progress. Independent 22 be reviewed for acceptable closure of the degraded equipment issue. those Condition Reports verification drafted. ,

Disposition outstanding issues in accordance with 10CFR50.59 and needed to support core Generic Letter 91-18. load. 7 Review 20% of the Condition Reports closed since January 1,1995 Complete the review In closeout Independent !

which are associated with PSA safety significant systems for degraded prior to core load. verification. verification draf ted.

23 equipment operability issues to ensure that we have adequately '

identified and dispositioned operability issues.

Note: This has been expanded to a 100% review of PSA safety significant systems.

Page 3 j i

u.__m_-___ __u_-.-____m_ __1 _m___ m __ __._w.__.__m._ __ _ _ _ _ - __1 r____.___2-= __m-c- -" _--m

Complete an additional Outage Safety Review for the startup phase of Complete the review In progress. Draft independent ,

the outage. prior to core load. verification supports 24 core load.

Revise ORT-3 and DCS 3.1.11 to ensure Technical Specification Complete the revisions COMPLETE. FINAL 15.4.6.A.2 testing includes dynamic loading of the EDG with prior to core load. INDEPENDENT 26 sequenced loads.

~ ' '

VERIFICATION '

SUPPORTS CORE LOAD.

Test all EDGs in accordance with revised ORT-3 and DCS-3.1.11. Complete the testing of In progress. Independent 27 Return the electrical systems to normal alignment prior to leaving cold EDGs iaw revised ORT- verification drafted.

shutdown. 3 and DCS-3.1.11 prior to core load.

Upgrade Unit 2 operations checklists to include requirements for Complete the upgrade for One checklist Independent 34 initials, time, and date. During the review, verify that the checklists are checklists CL-7A and complete. verification drafted.

technically accurate. CL-1 E.

Include return to service testing in the plant schedule, both outage Complete prior to core COMPLETE. FINAL and nonoutage. Ioad. INDEPENDENT 37 VERIFICATION SUPPORTS CORE LOAD.

Modification 96-033 - replace control power transformers on Motor Prior to core load, In progress. Independent Control Centers 2B32 and 2B42. ,

complete the 67 control verificatior. drafted.

power transformers 38 identified in the Safety Evaluation Report dtd 9/25/96 to be done during U2R22.

Modification 90-048 - replace Horic Acid and Reactor Makeup Conditionally accept Conditionally FINAL Water totalizers, replace the CVCS control switch, replace flow prior to core load accepted. INDEPENDENT indicators, and refurbish flow controllers. This resolves an (needs PMT after core VERIFICATION 39 Operator workaround issue. load). SUPPORTS CORE LOAD.

Page 4

i Modifiesti:n 94-097 - rem:ve six RCS 1:op drcin ytives. Ccmpletz the Izstcllation FINAL

l installation prior to complete INDEPENDENT ,

core load (awaiting (awaiting VERIFICATION ;

40 RCS leak test as PMT). RCS leak test SUPPORTS CORE as PMT). LOAD.

Modification 92-141 - relocate the RHR flow control valve Accept priot to core COMPLETE. FINAL ,

controllers on 2CO3 for human factoring. Ioad. INDEPENDENT

41 VERIFICATION '

SUPPORTS CORE LOAD.

Modification 96-073 - seismically upgrade CCW, SI, RllR, and Accept prior to core COMPLETE. FINAL RHR/ letdown piping supports and remove an AFW snubber. Ioad. .

INDEPENDENT 42 VERIFICATION SUPPORTS CORE LOAD.

Modification %-022 -install a new 125 VDC feed to 480V Accept prior to core COMPLETE. FINAL safeguards bus 2B03. load. INDEPENDENT 46 VERIFICATION SUPPORTS CORE LOAD.

Work Orders 9601506,9602502,9603921,9611267,9611278, and Complete prior to core In closeout FINAL 9611755 - replace proximity switches and targets with an improved load. verification. INDEPENDENT 60 design and overhaul the Fuel Transfer Cart to enhance control system VERIFICATION

' operation. This resolves an Operator workaround issue. SUPPORTS CORE LOAD.

Work Orders 9613568 and 9613569 - provide bonnet pressure locking Complete prior to core Awaiting PMT Independent 61 niief for the SI-857A and SI-857B valves (interface valves between Ioad. (scheduled verification drafted.

RHR and Iligh liead SI) on Unit 2. week of April 7,1997).

Work Order 9606626 - reinstall switches on the Unit 2 Containment Complete prior to core COMPLETE. FINAL hatch third door to allow monitoring of door status. load. INDEPENDENT 65 VERIFICATION SUPPORTS CORE LOAD.

Page5

. _ .. . .~. . . - ..

Work crder 9611052 - replace the 2P-10B switch, the "B" RilR Cemplets prior is core COMPLETE. FINAL .

Pump control switch. Ioad. INDEPENDENT ,

66 VERIFICATION -

SUPPORTS CORE LOAD.

Conduct roundtable discussions with all MSS \SS\DTA personnel ' Complete prior to core in progress. Draft independent ,

regarding conservative decisionmaking, Technical Specification load. verification supports !

76 interpretations, and lessons learned from recent regulatory core load.

communications and perspectives. Review outlier Technical Specification interpretations for interim applications.

9 i

Page 6

. . _ _ _ _____.________.______________________________________________________________

NPL-97-0159, Forwards Documentation for Review to Support Restart Issues Identified on Unit 2 Startup Commitment List

Contents

Text

Subject:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

Navigation menu

NPL-97-0159, Forwards Documentation for Review to Support Restart Issues Identified on Unit 2 Startup Commitment List

Text

Subject:

REFERENCES:

REFERENCES:

REFERENCES:

REFERENCES:

Navigation menu

Search