ML20203D056

Summary of 860326 Meeting W/Util & S&W in Bethesda,Md Re Status of Station Licensing Actions & Expanded Safety Sys Facility.List of Meeting Attendees & Related Info Encl

ML20203D056
Person / Time
Site:	Oyster Creek
Issue date:	04/12/1986
From:	Donohew J Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TAC-46466, TAC-59830, NUDOCS 8604210411
Download: ML20203D056 (31)

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UNITED STATES h,

NdCLEAR REGULATORY COMMISSION j

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WASHINGTON, D. C. 20555 e8

,o April 12,1986

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Docket No. 50-219 LICENSEES:

GPU Nuclear Corporation Jersey Central Power and Light Company FACILITY:

Oyster Creek Nuclear Generating Station

SUBJECT:

FERRUARY 1986 PROGRESS REVIEW MEETING ON LICENSING ACTIONS AND THE MEETING OF MARCH 26, 1986, ON THE STATUS OF THE EXPANCED SAFETY SYSTEM FACILITY On Wednesday, March 26, 1986, at NRR Headquarters, Bethesda, Maryland, a meeting was held with GPU Nuclear (the licensee) to discuss the status of station licensino actions and the status of the Expanded Safety System Facility (ESSF) planned by the licensee for Oyster Creek.

- is the list of the individuals that attended the meetings.

The following is a summary of the significant items discussed and the actions taken or proposed. References will be made to Cycle 11 Refueling (Cycle 11R) outage which is scheduled to begin April 1986 and end in October 1986. is a marked up copy of the staff's Licensing Actions Report Extended (LARE) dated March 23, 1986, for Oyster Creek. The markup, to update the LARE, resulted from the discussion on each item in this meeting. The status of each item is given in the column " STAT" on the right-hand side of the LARE sheets. The status in that column is the following:

"01" means licensee, "07." means staff's reviewer, "03" means staff's Project Manager, "04" means action completed and "05" means staff's Project Manager has licensing action in concurrence. is a listing of high priority licensina actions. is the overall status of licensing actions.

1.0 Exoanded Safety Svstem Facility (ESSF),

On Friday, September 20, 1985, the first meeting to discuss the status of the ESSF planned by the licensee for Oyster Creek was held at NRR Headquarters, Bethesda, Maryland.

The ESSF was proposed to be built at Oyster Creek by the licensee in its letter of March 11, 1985.

In that letter, the licensee described the ESSF and stated that the ESSF would enhance the safety capabilities of Oyster Creek, improve its overall operational capability and reliability and help ensure that Oyster Creek can achieve its exoected full licensed lifetime. The licensee requested the staff's comments on the ESSF, including design criteria, use of surplus equipment and implementation as not involving an unreviewed safety question under 10 CFR 50.59. The staff responded in its letter l

of April 16, 1985. The ESSF is not required by the staff.

8604210411 860412 PDR ADOCK 05000219 P

PDR

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. In its letter of March 11, 1985, the licensee stated that it intended to keep the staff up-to-date on the progress of the ESSF. This first meeting on the status of the ESSF was on September 20, 1985, to discuss the design of the foundation of the ESSF.

This March 26, 1986, meeting is the second meeting on the status of the ESSF. Attachment 3 is a copy of the material handed out by the licensee. This includes the acenda for the presentation by the licensee.

The last 5 pages in the Attachment are from the licensee's presentation in the September 20, 1985, meetino.

The licensee has been doing pile load testing in January 1986 at the site for the ESSF. This was discussed in the previous meeting on the ESSF. The licensee found the soil looser than expected. The depression in the soil due to vibroflotation of the soil went outside the area expected by the licensee.

The licensee will be relocating existing oiping in the ESSF building area where possible and supporting the existing oiping which cannot be relocated. This will avoid damage to the pipino during the vibroflotation of the soil to compact the soil. The pipinn supports will be removed from the piping after the soil is compacted and this piping will then be better supported by denser soil than exists now.

The old pipe of the plant service water system that will be under the ESSF buildina will be replaced by new pipe in the Cycle 11R outage.

The licensee's criteria for compacting the soil is that the peak velocity for acceleration to the Reactor Building is less than 0.2 feet /second. The actual peak velocity for accelerations during the pile load testino were 0.02 feet /second.

The design for the ESSF building and its contents are being put in a computer data base. The drawings for the ESSF are generated by a computer software orogram. The progran keeps track of all components of the ESSF (e.g., pipes, valves, ducts, cabinets, etc.) and the paper work on each item.

2.0 Control Room Habitability (TAC 46466)

The licensee stated that procedures require the control room to be notified when a chlorine tank car comes onsite. This is done by the station security as it allows the car within the security fence. The control room operators will by procedures put the control room ventilation on minimum air inflow (450 cfmi,to pressurize the control room acainst leakage into the control room. This is the minimum air

j mode for the control room and was assumed by the licensee for its calculation of the minimum time for the control room to reach toxic I

chlorine concentrations following rupture of a chlorine tank car or of a chlorine tank at the chlorination facility onsite. This calculation was submitted by the licensee in its letter dated August 16, 1985.

The licensee stated that if the chlorine monitor in the chlorine facility alarms in the control room, the emerqency operating procedures instruct the operators to don protective clothing and place the control room ventilation in the minimum air mode. There is no planned isolation of the control room. This would alloc air inleakage into the control room from the air space surrounding the control room.

Drawing 19702 of the plant drawinas shows the chlorinaton facility which is at ground level on the opposite side of the turbine building from the control room. Chlorine gas is heavier than air and the control room intake is above the turbine building.

The licensee stated that there was an event in the summary 1984 durina the Cycle 10R outage in which chlorine cas was released from the chlorination facility. The gas entered the turbine building but did not enter the control room.

The licensee stated that its calculation for the time to reach the chlorine toxic concentration in the control room was based on a straight line path to the control room intake. This straight line oath is through the turbine buildina. The calculations were for the worst wind speed and wind stability class for lack of chlorine 1

dispension in transit to tiie control room intake.

3.0 Cancellation of Modification to Install Pressure Relief Vent in Standbv Gas Treatment System (SGTS) Purae and Vent Exhaust Duct (TAC 598301 In its letter dated May 14, 1984, the licensee committed to two modifications: the 5-second time dalay to open the SGTS inlet valves was for the protection of the SGT3 and the pressure relief vent in the SGTS ducts was to protect the ducts and the SGTS filters.

The licensee stated that the 5-second time delay was to protect both 4

the SGTS and. the SGTS filters. The pressure relief vent'was only to protect the ducts. The 5-second time delay has been installed. The licensee, in it letter dated Sentember 24, 1985, proposed to cancel the modification to install the pressure relief vent because it stated that this modification was, on reexamination, not needed to protect the ducts.

4.0 Uodated NRR Licensing Action Report Extended (LAREl Dated 03/23/86

. has the updated LARE for Oyster Creek. The updating was done during the discussion on each licensing action in this meeting.

The licensing actions are listed by TAC number (left hand column of LARE).

i 4

. The LARE is a print out from the staff's PC licensing action trackina system. The LARE contains references to future licensing actions and future submittals to be submitted by the licensee. These future actions have TAC numbers 0CXXX in Attachment 2.

5.0 High Prierity Licensina Actions Attachmenc 4 is a list of the high priority licen3ing actions.

These were taken from the overall list of licensino actions in.

6.0 Overall Status of Licensing Actinns is the overall status of licensing actions.

7.0 Next Meetina The March 1986 Progress Review Meetina is expected to be held at the station site on April 22, 1986, and at the licensee's Headquarters in Parsippany, New Jersey, on April 23, 1986.

(IvW 0 bac(hkN.Donohew, Pro [ectManager C

(!. BWR Pro.iect Directorate #1

' Division of BWR Licensing Attachments:

1.

List of Attendees 2.

Staff's Updated LARE dated 3/23/86 3.

Material Handed out by

{

Licensee on the ESSF 4.

High Priority Licensing Actions 5.

Overall Status of Licensing Actions cc:

R. Bernero W. Hodges R. Houston G. Hulman J. Zwolinski M. Srinivasan G. Lainas D. Vassallo B.D. Liaw C. Grimes I

5

cc:

Ernest L. Blake, Jr.

Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 1800 M Street, N.W.

Post Office Box 445 Washington, D.C.

20036 Forked River, New Jersey 08731 J.B. Liberman, Esquire Commissioner Bishop, Liberman, Cook, et al.

New Jersey Department of Eneroy 1155 Avenue of the Americas 101 Commerce Street New York, New York 10036 Ne vark, New Jersey 07102 Eucene Fisher, Assistant Director Regional Administrator, Region I Ditision of Environmental Quality U.S. Nuclear Regulatory Commission Department of Environmental 631 Park Avenue Protection King of Prussia. Pennsylvania 19406 380 Scotch Road Trenton, New Jersey 086?8 BWR Licensing Manager P. B. Fiedler GPU Nuclear Vice President & Director 100 Interpace Parkway Oyster Creek Nuclear Generating Parsippany, New Jersey 07054 Station Fost Office Box 388 Depety Attorney General Forked River, New Jersey 08731 State of New Jersey Department of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625 Mayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731

0. G. Holland Licensing Manager Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731 j

FEBRUARY 1986 PROGRESS REVIEW MEETING March 26, 1986 N=me

-Affiliation R. Green NJBRP*

J. Donohew NRC/NRR/DRL M. Laggart GPUN EXPANDED SAFETY SYSTEM FACILITY MEETING March 26, 1986 Name Affiliation R. Green NJBRP*

J. Donohew NRC/NRR/DRL M. Laggart GPUN#

E. Wallace GPUN B. Gutherman S&W Engineering G. Brown S&W Engineering D. Jerko GPUN T. Ott S&W Engineering A. Varela NRC/ Region I R. Green NJBRP*

• State of New Jersey Rureau of Radiation Protection

1. GPU Nuclear Corporation j

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e ATTACHMENT 3

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\\ ~~ R O J U C -~ O N NEED FOR ESSF

• lNCREASE RESERVE CAPACITY OF EXISTING SAFETY-GRADE DIESEL GENERATORS

• PROVIDE SPACE FOR FOR FUTURE PLANT MODIFICATIONS 9

REASON FOR MEETING Ii

• KEEP NRR AND REGION I STAFF UP TO DATE ON ESSF PROGRESS 3 roc EC~~

OBe EC-~ V ES 3 rom EC-~

A33ROAC-

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J ES G \\

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0 3J EC-~ V ES TRANSFER SOME BOP ELECTRICAL LOADS TO ESSF POWER' SUPPLY IN ORDER TO:

~

• INCREASE CLASS IE POWER CAPACITY MARGIN f

• REDUCE LOAD SHEDDING PROVIDE ADDITIONAL FLEXIBILITY OF ONSITE & OFFSITE POWER SOURCES ENHANCE OPERATOR ACTION FOR ACCIDENTS WITH AUTOMATIC LOAD SEQUENCERS PROVIDE SPACE FOR FUTURE EXPANSION 3 roc EC-~

A33ROAC-PHASED CONSTRUCTION ILD A NON SAFETY-GRADE. FACILITY MAINTAINING MANY SAFETY-

• PHASE I: BU GRADE DESIGN FE^TURES AND PROVIDING FUTURE UPGRADE CAPABILITY i PHASE 2: MODIFY TO SAFETY-GRADE (IF NEEDED)

l 3 roc EC-~

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i SUPERSTRUCTURE METAL SIDING TO SERVE AS -FORM WORK FOR FUTURE CONCRETE WALLS l

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PROVIDE TRACEABILITY OF DOCUMENTATION FOR FUTURE UbE' I

IMPOSSIBLE WHERE FUTURE PHYSICAL MODIFICATIONS ARE

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OR IMPRACTICAL, IMPLEMENT IN INITIAL DESIGN

PIPE, DUCT, CABLE

TRAY, CONhij T. SUPPORT DESIGN INSTALL.

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l MECHANICAL / ELECTRICAL SEPARATION 1

INTEGRATED DATA BASE

• COMPONENT STATUS UPDATES INTELLIGENT BASE DOCUMENT CAD DRAWINGS USEFULNESS TO OPERATIONS AND MAINTENANCE PERSONNEL i

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OFFICE SLOG.

REACTOR SLDG.

High Priority Actions dated January 22. 1986 if 1986 Staff Licensee /se 1

TAC Title 8 ranch Target Date Status #

i 60153 Cancel Modification Plant Sy.sem February

• 02 pp Torus Pool Temperature Monitoring I

60152 Cance) Modifications Plant System February

• 02 gg Torus Pool Thermal

)

Mixing 01 59935 Revise Operability of Reactor System May low-low RCS Water Level I

l 59530 Cancel Modification to P1 ant System February

• 02 gg Install Pressure Relief N

j 59829 Ca'ncel Modification to Plant System February

• 01 i(

Upgrade N2 Purge / Vent System 59828 Cancel of Purge / Vent Engineering March

• 01 Valve Replacement i

59758 Scope Change for Reactor System March

• 03 Recirculation Loop Interlock, II.K.3.19 59400 Defements from Cycle BPDil February

• 01 11R Outage i

I 59342 Exemption to RCS Vents Reactor System March

• 03 58018 Generic Letter 84-09 Plant System February

• 02 58004 Discrepancy in SE)**

Integrated Safety May 01 Drawings Assess Directorate 49394 Tornado Missile Danage Plant System March ***

02 f

- SEP l

49397 Emergency Condenser BWD#1 J une***

03 Isolation 49398 Seismic Design - SEP**

Integrated Safety December 1985 01 4

Assess Directorate t

i 1

I I-

• P

~

s s

' 1986 Staff Licensee /se TAC Title Branch Target Date Status #

46466 Control Room Reactor System February

• 02 Habitability 02 11270 Inservice Testing Engineering 01 08100 Appendix I TS BPD#1 Apri1*

• Actions involved with Cycle 11R outage which begins April 1986.

• • Involved with licensee's work on IE Bulletins 79-14/02 and/or package is at Director's desk.

"* Old SEF reviews with licensee's submittals with reviewer and needed for f

FTOL conversion.

• "* This needs to be scheduled by the branch because plant is in the 7th year of the 10 year cycle.

(

1. 01 = licensee, 02 = staff reviewer, 03 = ORPM, 05 = licensing action in j

(

~

concurrence, z

1. 1. PM writing licensing actionwithout safety evaluation from branch.

sl'(.

3 1y

l t

4 l

STATUS OF LICENSING ACTIONS March 26, 1986 l

l Technical Assianment (TAC)

TAC Numbers Chance

• Active as of 10/1/85 62#

i New TAC since 10/1/85 27

+5 Total TAC 89

+5 i

Completed TAC since 10/1/85 (04) 32

+10 TAC needing Licensing response (01) 14

+?

TAC under staff review (02) 21

-11

'T'C with staff Project Manager (03) 09

-1 A

TAC in staff concurrence (05) 13

+5 Total TAC 89

+5 j

Future Work 17 106

• From previous monthl,v progress review meetino l

1. Starting from TAC 59663 LAR dated 10/1/85 O

' APR 121986 The LARE is a print out from the staff's PC licensing action tracking l

system. The LARE contains references to future licensing actions and future submittals to be submitted by the licensee. These future l

actions have TAC numbers OCXXX in Attachment 2.

l 5.0 High Priority Licensino Actions l

l is a list of the high priority licensing actions.

These were taken from the overall list of licensing actions in.

6.0 Overall Status of Licensino Actions is the overall status of licensing actions.

7.0 Next Meeting The March 1986 Progress Review Meeting is expected to be held at the station site on April 22, 1986, and at the licensee's Headquarters in Parsippany, New Jersey, on April 23, 1986, ack N. Donohew, bro.iect Manager RWR Pro.iect Dire torate #1 Division of RWR Licensing Attachments:

i 1.

List of Attendees P.

Staff's Updated LARE dated 3/23/86 3.

Material Handed out by DISTRIBUTION Licensee on the ESSF i_ Docket. -

4.

High Priority Licensing Actions NRC PDR 5.

Overall Status of Licensing Actions Local PDR RWD#1 Rda cc:

R. Bernero W. Hodges JZwolinski R. Houston G. Hulman OELD J. 7wolinski M. Srinivasan JDonohew G. Lainas D. Vassallo EJordan B.D. Liaw C. Grimes BGrimes ACRS (10)

CJamerson OC file Y

Y DRL:PD#1 o lew:tm JZwolinski

/86 4/p/86 l

l