ML20055A416

Order Delineating Questions to Be Addressed Re Restart Requirements,Aslb Findings & Testimony Presented at Hearing

ML20055A416
Person / Time
Site:	Three Mile Island
Issue date:	07/14/1982
From:	Shoemaker C NRC ATOMIC SAFETY & LICENSING APPEAL PANEL (ASLAP)
To:
References
ISSUANCES-SP, NUDOCS 8207160304
Download: ML20055A416 (32)

Text

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UNITED STATES OF AMERICA ,

NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING APPEAL BOARD Administrative Judges:

Gary J. Edles, Chairman .

SERVED JUL151982 Dr. John H. Buck Dr. Reginald L. Gotchy

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In the Matter of )

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METROPOLITAN EDISON COMPANY ) Docket No.l50-289 - SP (Restart)

(Three Mile Island Nuclear Station, Unit No. 1) )

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ORDER July 14, 1982 As we indicated in our order of May 17, 1982, oral argu-ment on plant design, procedures, and separation issues is tentatively scheduled for September 1, 1982. In the course of our review of the record and the parties' briefs on those

! issues, we have identified a number of questions which we I believe should be addressed. They concern the status and/or details of various restart requirements, certain of the Licen-sing Board's findings, and testimony presented at the hearing.

To better focus our review at oral argument, we believe it

! would be helpful to obtain the information in writing in advance of oral argument.

4 8207160304 820714 PDR ADOCK 05000289 3

G PDR b [d2

Some of our questions may involve simply clarification of the existing record; others request information not available at the time of the hearing. The staff shall provide an initial response to each question marked with an asterisk. Licensee

! shall provide an initial response to all questions not marked with an asterisk. Because the responses may include both evidentiary material and comments, we request that all answers be provided in affidavit. form. All parties may reply to initial responses in the form of comments or affidavits. Our questions follow.

I. Update of Restart Requirements Appendix A to this order is a list of restart items 1 /

for which we would like information as to current status and, j where applicable, present estimates of completion dates.

In each case, a simple statement that the item has been com-pleted or an estimate of the percentage of completion and an expected completion date will be sufficient.

l l 1/ The " status list" of restart items was formulated from the requirements for TMI-l restart as stated in the l Commission's " Order and Notice of Hearing," CLI-79-8, l

10 NRC 141 (August 9, 1979). The list itself was attached to the staf f's TMI Restart Certification, SECY-82-250, dated June 16, 1982. For the parties' convenience, a copy of the status list is included as Appendix B. Our request for an update in Part I pertains to only those items listed in Appendix A, however.

II. Detailed Questions Concerning Some of the Items Listed in the TMI-Restart Certification (Status List, Appendix B)

A. In letters dated April 22, 1982 and May 13, 1982, the licensee notified this Board that certain steam and water tests exhibited valve instability that resulted in damage to the safety relief valve. Throughout the hearing, licensee maintained that the feed and bleed mode of forced core cooling re-lied upon these valves to provide a release pathway for excess coolant. In light of these tests results, how does the licensee plan to ensure that safety relief valves are cap-able of performing their function during feed and bleed when they may be called upon to open and close frequently with both steam and water flow mixtures?

l B. The status list indicates that the installation of the Emergency Feedwater (EFW) automatic initiation is completed as control grade equipment (Item A.8.2.1.7a) but that further modifications up to safety grade will be partially completed by August 1982, and a footnote indicates that additional long term modifications are scheduled for the first refueling after restart. During the hearing, the staff testified that emergency feedwater modifications should be completed by late 1982 (Ross, Tr. 15,577).

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1. Which, if any, of the modifications discussed in Paragraphs 1028-1034 of the partial initial decision (PID),

LBP-81-59, 14 NRC 1211 (1981), will not be completed before restart?

2. What are the reasons for the delay beyond the completion date estimated by the staff during the hearing?

• C. In Paragraph 880 of the PID, the Licensing Board left resolution of the issue of separation of the new wide-range containment building radiation monitors to the staff. Has this issue been resolved? If so, state where the monitors are to be located.

• D. In CLI-79-8, 10 NRC 141 (1979), the Commission re-quired, inter alia, that long-term action 2.1.9 of the table in Appendix B of NUREG-0578 be completed by the licensee as "promptly as practicable." The status list (Item 2.1.9b) indicates that the Guidelines have been submitted with the procedure implementation to be completed by the first refueling after October 1, 1982. What progress has been made by the staff in its review of licensee's submittals?

E. During the hearing, the licensee indicated that the high point vents were planned to be installed prior to restart (Tr. 16,580). NUREG-0737 requires the installation to be com-plete by July 1, 1982. The status list indicates that the com-t pletion date is "to be determined." What progress has been made i

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in complying with the requirements of NUREG-0737 for the in-sta11ation of high point vents? Are the vents and their con-trols fully safety grade? If the high point vents will not be installed prior. to restart, what is the justification for allowing operation of TMI-l before the vents are installed?

I III. Questions Based on Licensing Board Requirements and Findings

• A. In Paragraph 628 of the PID, the Licensing Board discussed the installation of shield walls in the motor control centers. What is the status of staff review of this plant i

modification? What was the source term used in determining the adequacy of the shield walls?

B. In Paragraph 771 of its PID, the Licensing Board directed the staff to verify that procedures to connect the pressurizer heaters to the diesels include provisions to N

assure that the heaters would not be reconnected to onsite power until stabilization of the event that caused their disconnection. The status list attached to SECY-82-250 indicates that this item is complete. What provisions have been included in the procedures to comply with the Licensing Board's direction?

C. PID Paragraph 943 listed measures that have been or will be taken at TMI-l to improve protection against small break LOCAs. One of those measures was the improvement of the HPI system by adding cavitating venturis and cross-connection lines.

4 It was also stated that the system being installed will auto-matically perform the balancing of HPI flow. How is this to be accomplished and what is the completion status of these HPI modifications?

D. In Paragraph 1064 of its PID, the Licensing Board directed the staff to certify to the Commission that the licensee has made reasonable progress in initiating a program for long-

term solution of the steam generator bypass logic problem. What progress has been made by the licensee in solving this problem?

l What interim methods will be used to ensure that plant operators are aware of the problem and the actions to be taken in the event of isolation of both steam generators?

il E. The Licensing Board has directed the staff (PID Paragraph 1162) to certify to the Commission a report on li-censee's compliance with CLI-80-21, 11 NRC 707 (1980) as it relates to safety equipment functioning in a radiological en-vironment in a TMI-2 type accident. On January 28, 1982, the staff submitted such a report to the Commission. This certified the status of licensee's compliance as of January 30, 1981.

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! What is the current status of compliance by the licensee with CLI-80-21 for qualification of safety equipment for a harsh environment? This information should include all of the para-meters addressed by IE Bulletin 79-OlB and its Supplements, such as temperature, pressure, chemical spray, radiation, aging, and humidity. Also information concerning the environmental qualification of the various components of the emergency feed-water system should be provided with an estimate of the schedule I

j for full qualification of this system.

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. tr As stated in Paragraphs 1163 and 1168 of t'he PID, the Licensing Board has placed six conditions for restart involving material aging and other environmental qualifications of some equipment. These conditions were apparently originally presented in the staff's testimony with some objection by the licensee.

However, a final rule entitled " Environmental Qualification of Electric Equipment"  ! suspends the deadline for environmental qualification of safety-related electric equip-ment at operating plants. What effect will this rule have on licensee's schedule for completion of equipment qualification?

• F. The Licensing Board imposed several conditions con-cerning the establishment of an accurate floed level. (PID, Paragraph 1174.) The staff was directed to review (1) licen-see's flood level calculations and (2) operational limitations to ensure that the actual level does not exceed the maximum flood level. In particular, the staff was directed to review the ability to enter the recirculation mode under all postu-lated conditions. What is the status of this review? What are the results?

If the licensee's maximum flood level is not conservative, the Licensing Board directed that a new flood level be deter-mined and all equipment important to safety relocated above the new flood level by June 30, 1982. What progress has been made in complying with these conditions?

2_/ 47 Fed. Reg. 28363 (June 30, 1982).

• G. In Paragraph 1180 of its PID, the Licensing Board discusses the confusion concerning the environmental quali-fication of equipment needed to achieve cold shutdown. The Licensing Board also directed that the Commission be informed if licensee does not plan ~to qualify the equipment in accordance with Supplement 3 to IE Bulletin 79-OlB. On January 28, 1982, the staff informed the Commission that it was not aware of plans by the licensee to qualify equipment needed to achieve cold shutdown. What is the current staff position with regard to compliance with Supplement 3 to IE Bulletin 79-OlB for an environmentally qualified pathway to achieve cold shutdown?

If this requirement is deleted and the subject incorporated into Unresolved Safety Issue A-45 as proposed in SECY-82-207A,

" Environmental Qualification of Safety-Related Electric Equip-ment for Nuclear Power Plants" (June 9, 1982), how is adequate protection of the public health and safety provided at TMI-1 if the plant is operated while this issue is being resolved?

• H. In PID Paragraph 640, the Licensing Board stated that inadequate core cooling procedures were under review by the staff and that revised submittals had been required from l

the licensee. It was indicated that the staff had not completed its review at that time but was confident that procedures

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t a, acceptable for TMI-l restart without reliance on water' level i'

measurement could be developed. What are the results of:the i staff review of the licensee's inadequate core cooling pro-

dures?

I. In a footnote to Paragraph 919 of the PID, the Licensing Board indicated that the licensee planned to per- ,

! form an in-plant communications study in 1981. What is the status of that study? If completed, please briefly summarize results and present status of implementation. -

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• J. In PID Paragraph 1000, the Licensing Board specified that TMI-1 be included by the staff in generic reviews of systems interactions. What progress has been made in com t plying with this requirement?

i l K. The Licensing Board indicated in PID Paragraph 1264 l

2 that a tunnel-like barrier for personnel passage between the Unit 1 control tower and the Unit 1 auxiliary building will l be completed before restart. What progress has been made in completing this modification?

• L. The Licensing Board (PID, Paragraph 935) discussed the absence of analyses that would indicate the time allowed for operator action to initiate either HPI or EFW flow inEthe event of a small-break LOCA at the reactor coolant pump (RCP)~ suction.

i The Licensing Board specified as a condition of restart that i

this missing analysia be performed and submitted to the staff l , ,

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! i for review. The staff was required to bring the matter to the attention of the Commission if the results were unaccept-able.

on June 4, 1981, the licensee submitted to the TMI Licensing Board a letter from B&W which indicated that "a i

pump suction break will result in the loss of lower quality fluid which will deplete system inventory at a higher rate.

Thus at the time of AFW actuation the RCS inventory will be less for the pump suction line break than for the pump dis-charge line break." However, no statement as to the decrease in the maximum 20 minute time for the operator to react was given. Staff witness Jensen,on the other hand, stated in his affidavit 1/ that the reduction in available time for operator I decision would come about "because the reactor coolant piping i

is lower at the reactor coolant ppmp suction than at the pump j discharge and more reactor system water might be lost out the break." We do not understand the reasoning behind this state-i ment or what significance it has to the dynamic situation pre-l sent during a LOCA. Mr. Jensen gives no indication of the l

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3/ This affidavit (dated November 24, 1981) was initially pre-sented during the Rancho Seco (Sacramento Municipal Utility District) proceeding and transmitted to the TMI Licensing Board by the licensee on December 30, 1981. The statement concerning the lower elevation of the suction piping re-lative to the discharge piping was repeated in an affidavit by Mr. Jensen on January 22, 1982.

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i difference in time involved for operator decisions between a i

break on the discharge side of the reactor coolant pump versus the suction side. We recognize that the Licensing Board vacated I its request for further analysis on this subject A/ b ut we request the staff to explain fully the conclusions Mr. Jensen reaches on the last page of his January 22, 1982 affidavit that "a minimum of 20 minutes would be available to the operator to actuate HPI and prevent core uncovery for breaks in the pump suction as well as at the pump discharge, even if all feed-

) water is temporary [ sic ] lost." ,

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Unpublished memorandum and order of January 26, 1982, Modifying Partial Initial Decision of December 14, 1981 at p. 7.

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IV. Clarification of Testimony Presented at the Hearing 4

• A . Staff witness Jensen testified at the hearing (Tr. 5501) that, if the EFW system was available, one HPI pump would be adequate to cool the core for all small-break LOCAs. What analysis was performed to show that natural i

circulation would occur with only one HPI and one EFW pump?

Would the natural circulation be liquid or boiler-condenser mode?

B. In the event that the pressurizer heaters fail to operate while the plant is operating at full power, (1) how much time would it take to achieve RHR system initiation conditions and then cold shutdown?

(2) how would pressure control be performed during I cooldown to conditions allowing RHR system operation?

(3) how soon after shutdown from full power con-

! ditions does the RHR system have sufficient decay heat removal capability?

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• (4) do any Commission offices have any data on I pressurizer heater failures? If so, what has been the

frequency of such failures?

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• C. Why did the steam safety valve associated with the damaged steam generator open twice during the steam generator

tube rupture event at the Ginna plant on January 25, 19827 What 2

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effect does this have on the position that the' pressurizer safety relief valves can be used for feed and bleed cooling without opening of the steam generator steam safety valves during a steam generator tube rupture?

D. What is the extent of the environmental qualification of the PORV block valve and its controls?

• E. What is the basis for requiring that the high-point vents be safety grade and have sufficient redundancy to minimize the probability of inadvertent actuation but not applying the same requirements to the PORV?

F. Describe the method for cooling the plant to RHR initiation conditions by feed and bleed cooling using only safety-grade equipment.

• G. Have any tests been conducted at the LOFT facility that provide information on the ability of feed and bleed to adequately cool the core? If so please state conclusions.

• H. In this record we have found no official staff defini-tion of the term " inadequate core cooling." However, one staff witness stated "when the two-phase froth level begins to drop below the top of the core, the exposed fuel begins to heat up and will ultimately reach temperatures at which fuel damage i

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occurs. This is inadequate core cooling." Testimony of Lawrence E. Phillips Regarding Water Level Instrumentation, fol. Tr. 10,807 at 3.

If the Phillips definition properly reflects the staff's position on inadequate core cooling, please state the bases on which this definition is formulated. If it does not represent

', the staff's position, please give the accepted definition with J

an explanation of the bases for adopting a different definition.

I. During RHR system operation, how is overpressure protection provided?

Initial responses shall be in our hands and the hands of those parties participating in this phase of the proceeding by close of business on Monday, August 9, 1982. All replies shall be delivered in the same manner by close of business on Wednesday, l

August 25, 1982.

It is so ORDERED.

FOR THE APPEAL BOARD

< O _;3D eA-d C. J Secr$n Slfoemaker etary to the Appeal Board

APPENDIX A .

Answers to be Supplied on the Following Items of the TMI-l Restart Certification Status List (Appendix B)

I. August 9, 1979 Order Requirements (CLI-7 9- 8 , 10 NRC 141)

A. Short Term Order Item 1 EFW Reliability la-3 Auto EFW Load to Diesels la-4 EFW Technical Specification la Additional Items 1 CWST Level Alarm 6 EFW Initiation Independent of AC

• 7 EFW Operability in Steam Environment 8 Cross-Tie Break Order Item 2 IE Bulletins

• 79-05A-2 Plant Transient Review 79-05B-3 PORV Set Point 79-05B-5 Anticipatory Reactor Trip (Safety Grade)

Order Item 4 Separation of TMI-1 & 2 (a) Liquid Radwaste (b) Gaseous Radwaste (c) Solid Radwaste (d) Sampling System

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Order Item 8 Lessons Learned - Short Term 4 2.1.1 Emergency Power Supply

- Pressurizer Heaters 2.1.3a Valve Position Indication 1 ~

2.1.3b Inadequate Core Cooling

- Existing Instrumentation & Saturation Meter 2.1.4 Containment Isolation i

j 2.1.Sc Install Recombiner 2.1.8c Iodine Instrumentation B. Long Term (LT) (NUREG-0737 numbers) l LT-1 (II.K.2.9) ICS FMEA Modifications t

• LT-2 Small Break Analyses LT-3 Lessons Learned Category B from NUREG-0578 2.1.3b (II.F.2.3) ICC Instrumentation

- Backup Incore Thermocouples (safety grade) 2.1.Sa (II . E . 4 .1) Dedicated H 2 Penetrations

- Install 2.1.6b (II.B.2) Plant Shielding l

! - Plant Modifications 2.1.7a (II.E.1.2) EFW Auto Initiation i - Safety Grade 2.1.7b (II . E .1. 2 ) EFW Flow Indication

- Safety Grade 4

2.1.8a (II.B.3) Post-Accident Sampling

- Modifications 2.1.8b (II.F.1) Radiation Monitors

- Effluent Monitors

- Iodine / Particulate Monitors Additional Items

1. 1 (II.F.1) Containment Pressure

1. 2 (II.F.1) Containment Water Level

1. 3 (II.F.1) Containment Hydrogen LT-4 Emergency Preparedness Emergency Communications

- Install control room emergency telephone j - Connect emergency telephone equipment to vital power Emergency Facilities

- Install high radiation monitoring alarm system II. ASLB Imposed Requirements (December 14, 1981 PID)

B. Plant Design, Modification and Procedures Findings l II.E. Pressurizer Heaters

- Demonstrate RCS pressure control w/HPI l

II.K Computer

- Incore thermocouple backup display (not safety grade) l I

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II.M Safety System Status Panel

- System Status Administrative Controls II.N Control Room Design

- Correct NUREG-0752 deficiencies II.P Systems Classification

- Upgrade Pressurizer Level Instrument Power Supplies II.Q EFW Reliability (see detailed question on long-term order Item B.2.1.7a)

- Safety grade automatic EFW control

- Install following long-term EFW modifications (a) EFW cavitating venturis (b) CWST level alarm (safety grade)

(c) OTSG high level alarm (d) Safety grade isolation of MFW on'OTSG overfill (e) Upgrade main steam rupture detection system to safety grade C. Separation of TMI-l and TMI-2 Findings III.B

• - Ventilation Separation Program (PID 2 1267)

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Till-1 ftESTARI CERitrICATf0N STATILi -

APPENDIX B I

• bOblIbI 9 1979 0 Olli)ER REQUlitEl!EllTS Inspection /Re flew Estimated Completion / . .

Item Description l len Type Licensee Statu_s_ S ta tus Remarks A. Sil0lti TERl1 Order i tem 1 EfW Reliability ,

la-1 Auto Initiation of Efil Mod Complete Complete Except power escala-Lion testing la-2 EfW Valves Fall Open flod Coupidte Conplete la-3 Auto Enl Load on Diesels ,

Hod Complete Complete except 6/02 tes ting 3

la-4 IFW Tech Specs Tech Specs procedure Chgs. Partially 9/02 Req. Complete la-S EfW flow Indication 11od il/A fl/A Licensee installing (control graile) safety grade inst. ^

IAW II.E.l.2

-la-6 EfW Procedures proceduies Complete Complete ila-7 EFW Valve Alignment Procedures Complete Complete

1 a-l) ErW Auto Start Annunciation Mod Complete Complete Except power escala-tion testing

la Additional Reliability Analysis itemsl 1 CWST Level Alann Hod IHL Items- .

Partially Complete 8/02 -

Cst. 7/U2 2 2 Endurance Test Test Comple te Complete .

3 Transfer of EFW Supply Procedures Complete Complete 4 ERI to Intact OTSG Mod Complete Compl ete 5 . Auto ETW Protection on loss Analysis Conple te Complete of Water Source I

la Additional items were not Orddr items; all but la-additional item 7 to be completed prior to restart.

IHL items-incomplete work list iteris (i.e., modification essentially complete). .

License amendment to be issued for changes to Technical ' Specifications prior to restart.

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e Inspection / Review Estimated Completion /

• Item Gescription item Tyg Licensec Status Status Remrks .

,6 . Enl Initiation Independent flod In' construction- Partially complete 2st. 8/82 Except llot of AC Cst. 7/02

• Functional Testing (!!FT) 7 Enl Operability in Steam - lbd -- -- Not required for Environment gar 3perfiUREG-0680 0 Cross-Tie Dreak Analysis Complete  !!an-destructive exan 7/82 of welds scheduled-7/82 lb En1 Independent of ICS lbd Complete Complete Ic Sugngigjl by Order Item 2 fl/A ft/A ti/A Id Small Dreak Analysis Analysis Complete , Complete le Operator Retraining Training Complete Complete Order Iten ;. IE Bulletins 79-05A-1 Accident Unders tanding Trainin9 Conplete Complete 79-05A-2 Plant Transient Review Inspection Complete Scheduled 7/82 7/02 79-05A-3 Transient Procedures Procedures Complete Complete 79-05A-4 Opera tin 9 Procedures Procedures Complete Complete .

79-05A-S Valve Position Review Procedures -- -- Valve 1ineup vert fica-tion at time of restart 79-05A-6 Containment Isolation 11od See Order Item 8 See Order Item 8 2.1.4 2.1.4 79-05A-7 ER1 Valve Procedures Procedures Complete ,

Complete 79-05A-8 ERf Operability Procedures Conplete Complete 79-05A-9 Transfer of Containment Procedures See Order Item 8 See Oroer Item 8 '

Liquids 2.1.6a 2.1.6a N 79-05A-10 Safety System Operability Procedures Complete Complete 79-05A-ll Personnel Actions-THI-2 -

Training. Complete Complete 79-05A-12 Prompt Reportin9 Procedures Complete Compl ete e

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Inspection / Review Estimated Completion / * -

• Item Des crip tion Item Type Licensee Status Status' Remarks 79-06B-1 tlatural Circulation Procedures Conplete Complete 79-058-2 Vessel Integrity Procedures Complete Complete "

79-058-3 PORV Setpoint Mod Conplete Partially Complete 9/82 79-050-4 lianual Reactor Trip Procedure Complete Complete

79-050-5 , Anticipatory Reactor Trip Mod Couplete Partially Complete 6/82 except power (Safety Grade) escalation testing 79-050-6 Prompt Reporting Procedures Complete Complete -

79-050-7 Tech Spec Changes Tech Specs Procedure changes Pending I 9/82 required i 79-05C-1 HCP Trips Procedures Complete Complete 79-05C-2 Small LOCA Analysis Analysis Cnmplete Complete 79-05C-3 Operatur Action-RCP Trips Procedure Complete Complete 79-05C-4 Reactor Trip Training Training Complete Complete 79-05C-5 Inadequate Core Cooling Analysis Complete Complete Order item 3 Emergency Preparedness '

-- Complete Complete (Short Term) order Item 4 Separation of THI-l & 2 . .

a) Liquid Radwaste

-Interconnection Isolation Mod Complete Scheduled 8/82 8/82, b) Gaseous Radwaste

-1.eak Test of Waste System Test Complete Scheduled 8/82 8/82

-Fuel llandling Duilding Mod IWL Items-Est, Pending D/82 Isolation '

7/82

-ruel llandling guilqing Ibd IWL llems-Est. Pending 8/02 Vdntilation Sys. Ibd. 7 / 11 2 c) Solid Radwaste

-Ilittman Sys. Installation Ibd Conplete Completc 8/02

-lHI-1/2 Trash Segregation Procedures Complete Scheduled 8/82 8/82 s d)Sampi1ng System

-Independent THI-2 Sanpling lbd Complete Scheduled 8/02 8/02 System I

llote 3, page 1 Inspection /R: view Estimated Completicn/ -

Item Description Item Type 1.lcensee Status Status Remarks -

Order item 5 Waste llanagement a) Liquid & Gaseous Sys. Analysis Complete Comp.{cte b)Snlid Radwaste

-low activi ty stor, tbd IHL items- Pending 0/02 expansion Est. 7/02 0'rder Item f>- tlanagerial Capability (All actions from this Order item verified completed by liRil (liUREG-0600 and Supp.1 & 2) willi following exceptions) a)ltanagement & Technical

, -Training manual Training Partially complete Partially complete 7/02 b)Sa fety Review

-Final Version of Procedure Procedure Procedure revision Pending 8/P2 on operating experience info. required c)licalth Physics

-Qnalification Records Training Complete Partially conplete 0/02 d)flDREG-0694 Items .

-l!.B.4 Training Records for Training Partially complete Partially complete 9/02 tiitigating Core Damage Order Item 0 Lessons Learned-Short Term (Long Tenn Lessons Learned Under LT-3) 2.1.1 Emergency Power Supply

-Pressurizer lleaters liod IWL Items-Est. . Partially complete 7/02 G/82

-PORV, Block Valve, Level Analysis Complete Complete 2.1.2 Relicf Valve Testing (Program Description only) Testing Comple te Complete 2.1.3a Valve Position Indication tbd IHL I tems-Es t. Partially complete 0/82 ,.

2.1.3b Inadequate Core Cooling ,

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-Exis ting Instrumentation Ibd Complete Partially complete 7/02

& Saturation thter 2.1.4 Containment Isolation tbd In construction Partially complete 9/02

'. EsL. 8/02 ,-

2.1.5a Dedicated Ilydrogen Penetra- Design Complete Complete tions -

2.1.5c Install Recombiner Ibd IHL Items-Est. Partially conplete (iiot required by e -

7/02 U/9/79 Urder) ,.

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Inspection / Review Estimated Ccmpleticn/ .

Status Itg - Ih:s crip tion Item Type 1.icensee Status _

. Remarks .; .

2.1.6a . Sys tene. Integri ty Testing Complete Compl ete Complete for restart,

• additional tests post 4 restart Plant Shielding 2.1.6b Analys is Complete Complete ,

2.1.7a CIM Auto initiation (Control Grade) Mod Complete Complete 2.4.7b Eru Flow Indication (Control Grade)

• Mod fl/A N/A Licensee installing safety grade inst.

IAW II.E.1.2; see LT 3 Iton 2.1.7b 2.1.0a Post-Accident Sampling Design Complete Complete 2.1.0b Radiation Monitors (Control Grade) Mod fl/A N/A Licensee installing a)floble Gas ibnitors final nonitors b)Radiciodine Monitors IAW II.F.1; see LT 3 c) Particulate /L f fluent Item 2.1.0b 11nni tors 2.1.8c Iodine Instrumentation tbd Complete Pending 9/82 2.2.la Shift Supervisor Procedures Complete Complete

, 2.2.lb Shift Technical Advisor Procedures . Complete ,

Complete 2.2.2a Control Room Access Procedures Canplete . Complete .

2.2.2b Onsite Tech Support Center Mod Complete Complete 2.2.2c Onsite Operations Support Ctr. Mod Complete Complete -

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4 fiUREG-0737 '

Olt inplemen- Inspection / Review Estimated Completion / -

ltem liescription ta t ion Da t e I.f censee Status Status Remarks B. L0 fig TERli (LT) (fiUREG-0737 CORRESP0flDIliG ITEll tillfl0 Lits ALSO LISTED)I LT-1 ICS fl1EA lbih TBD Testing-6/02 Partially complete 7/02 IlCK.2.9)

LT-2 Small Dreak Analysis 1/1/82 Generic program flRR review submitted L T-3 1.essons Learned Category B From t{UREG-0578 2X2 llelief 1. Safety;Nalve Testing (11.D.1.2) -Complete testing 4/1/82 Complete Generic report Generic EPRI Program under flRR' review

-Plant specific rept. 7/1/82 Est. 7/82 Pending flRR review 2.1.3b ICC Instrumentation (II.F.2.3) -Ilackup Incore T/C 1 / 1 / 11 2 In Construction- Pending 9/822 (saiety grade) 8/82

-Water level inst. Under TBD TBD TBD development 2.1.5a Ded. lip Penetrations

( I I..E .4.1 ) -Install 7/1/81 IWL Items-7/82 Partially complete 8/82 2.1.6b Plant Shielding .

(11.B.2) -Plant lbds 1/1/82 Procurement --

1st refuel after problems-TBD restart 2 2.1.7a EFil Auto Initiation (II.E.1.2) -Safety Grade 7/1/01 IWL Items-6/02 Partially complete 8/823 9

2.1.7b EDI Flow Indication -

(II.E.1.2) -Safety Grade 7/1/01 , Complete Pending 8/02 2.1.0a Post-Accident sampling t

(II.B.3) -11odi fications 1/1/82 In Construction- Partially ~ complete 9/822-D/02 I

lloard 12/14/01 PID found licensee had made reasonabic progress on all LT items except 2.1.9 2 3 Licensee's (conmitmentcommitment not yet accepted for conbiletion y staff) is first refueling after restart Additional LT mods first refuel after restart *

-c .

. . ,/

titlREG-0737 ~

OR Implemen- Inspectien/ Review Estimated Ccmpiction/ .

item Description htlon Date Licensee Status - Status

• Remarks .

2.1.0b Radiation flonitors (ll.r.1) -cont. Itadiation Ibnitors 1/1/fl2 in Construction- , Partially complete 9/82 ,

0 / 11 2

-Cf fluent Ihnitors 1/1/02 Testing-7/02- Pending 8/82 -

-lodine /Part. Ibnitors 1/1/82 Illt Items-6/82 Pendin'g 7/82 2.1.9b Transient and Accident Analyses ,

(l.C.1) -Guidelines 1/1/01 Guidelines Sub- Guidelines Under Doard requested staff mitted flRR Review to certify reasonable

. -Procedure implementation 1st refuel Generic Program Generic Program progress-Est. 9/82 a f ter Submitted Under NRR Review 10/1/82 2

Addt'1" #1 Cont. Press. 1/1/82 in Construction- Pedding 9/821

( I I .F ,ll) D/02 y

( ! ! . F.1-) #2 Cont. Water Level 1/1/82 IllL Items-7/82 Pending 8/02 (II.F.1)l3 Cont. Ilydrogen 1/1/82 In Construction- Pending TBDI TBD

, i4 1(CS Venting ist outage In Engineering- Under NRR Review TDDI (11.B.1) af ter 7/1/82 TBD 1 I-4 fmergency Preparedness (All actions from this Order item verified completed (NUREG-0746, Supp.1 and Inspection reports) with following exceptions and those items 1.lsted under Board's Emergency Planning PID) -

Emergency Communications

-Install control room IHL Items-6/U2 Pending emergency telephone 7/82 ,

i " Connect emergency telephone Complete Pending equipment to vital power 6/82 i Emergency facilitics

! -Install high radiation Testing-6/02 Pending monitoring alarm system- 7/02 l

lI Licensce's conunitment for completion is first refueling after restart 2

Additional itans were not Order items but are NUREG-0737 actions

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PID Inspection / Review Estimated Completion /

_I t e m _ De,s c r i p t ion Licensee Status . Status . Remarks it.E Pressurizer llcaters j,

-Demonstrate RCS pressure control 1 1 /112 Pending IIFT w/IIPI (para. 755) -

II.F Pressurizer (Pzr) llcaters Power

-Procedures for connecting Pzr ,

Complete Complete ficaters to diesel (para. 771) *

-Demonstrate Pzr heater connection See Order Item 8 2.1.1 See Order Item 8 to emergency bus (para. 772) 2.1.1 '

II.K Computer

-Operator reliance on computer ComplcLe Pending 11/82 (para. 865) 7/02 Pending , , License Condition

-Incore displaythermocouple (not safety grade) backup (para. 867) before 5% power-Est. 9/82 II.L In-Plant Instrunent Ranges See Order Item LT-3 See Order Item -

-Ef fluent monitors (para. 874-875) 2.1.0b long tenn LT-3 2.1.8b 1ong term II.M Safety System Status Panel ,

-Safety system valve lineup review See Order Item 2 See Order Item 2 At t'ime of restart (para. (199) 79-05A-2 79-05A-2 I*

-System status admin. controls Partially complete Pending flFT .

(para. 904)

II .it Control Room Design

-Correct ilVREG-0752 deficiencies Partia11y' complete Partially complete Short-term 9/82, LT (para. 914-915) deficiencies 1st refuel after restart (license condition) 11.0 Additional LOCA Analysis -

-Install llPI Cavitating Venturis Complete Partially completc 8/02 (para. 943) lilfT=llot functiorial Tes ting 9_,

kII) Inspection / Review Estimated Completion / "

Item 11escript ion Licensee Status Status' Remarks

>l I . I' Systene. C1 ass i fication .

-Ilpgrade Pressurizer Level Ins t. lWL ltens-7/l,12 Pending 0/02 l'ower Supplies (para.1001) testing 11 0 FD1 Reliability

-Sa fety grade automatic See renurks See remarks 1st refuel after Erli control (para. 1036) restart (license condition)

-install following) lont term Efil inods (para.1037 a)Eill cavita ting venturis lWL items-6/02 Complete except IWL 0/02 exce,.t ilFT A testing li)CilST Icvel alann (safety grade) See renurks See renurks 1st refuel after restart (license condition) c)0TSG high level alarm See remarks See remarks 1st refuel after .

restart (license condition) d) Safety grade isolation of Mal on See remarks See remarks 1st refuel af ter OTSG overfill restart e)tipgrade main steam rupture See remarks See renurks 1st refuel af ter detection system to safety grade restart (license condition)

-Propose means to prevent EIN Cst. 6/02 . tiRR Review Certify reasonante isolation due to rupture detec- Pending progress-Est. 9/02

• tion sys, failure (para,1064) . .

II.S Iloard questions Hi1RI:G-0694 I tems (para. 1132)

- 1.II. l .2-O rgan i za tion -

Complete Couplete ,

& management improsement ,

-1.C.7-ilSSS vendor review Partially complete Pending 11/02 of procedures

-I.1).1-Control room design See remarks See remarks See Board item review II.N. tiUREG-0752

-1.G.l-Low power tes ting Partially complete NRR Revi.ew Pending. During low power testing

-I.C.0-Monitoring of Selected Complete Coa.nlete Emergency Procedures

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Inspection /fleview Estimated Completion / *q Item Pes c rip t ion 1.icensee SLatus Status Remarks f.S ta f f certi fy satis factory Complete FfMA review 6/82

• 9/02 colapletion of s iren sys tem Staff review 9/82 testing ,

g. Communications drill to he Complete Complete lurid prior to restart ,

b.Certi fy to Conmission that il/A TEllA review 6/02 9/82 1.PZ school plans ard Advisc Conmission camp 1ete 9/82 lloa rd Paragraph 7011

'Sugges- W.Ti ve Ydrk' c6unty school fl/A Est. 9/82 Certification not tions districts should prepare required plans for mass care emergency responsibilities .

b.Sta f f should noti fy Conmis- See remarks See remarks Certification not sion within 1 yr. af ter required.To be res tart whether distribution completed 1 yr. af ter of r,I accomplished res tart c.11onicipalities should prepare il/A Est. 9/82 Certification not written plans to assist with requi,ed evacua tion d.Connission should direct See remarks See remarks Certification not staff to certify to report on .

required.To be status of various state, coupleted l yr, county & municipal plan after restart.

deficiencies (1 yr af ter. -

restart) t e

- l 'l- -

,