ML20064L291
| ML20064L291 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Brunswick |
| Issue date: | 04/16/1982 |
| From: | Houston R Office of Nuclear Reactor Regulation |
| To: | Novak T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20064E577 | List: |
| References | |
| FOIA-82-389, TASK-2.F.1, TASK-TM NUDOCS 8205170128 | |
| Download: ML20064L291 (1) | |
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DISTRIBUTICN:
Docket File 50-324 Docket File 50-325 ETSB Reading File
-- >pTSB Docket File ADRP Reading File Docket flos. 50-324/325 APR 1 6 1982 RLBangart PGStoddart 11El10RAr!DUM FOR:
Thomas !!. flovak, Assistant Director for Operating Reactors, DL FRO:::
R. !!ayne Houston, Assistant Director for Radiation Protection, DSI
SUBJECT:
BRUNSilICK STEAM ELECTRIC PLAtlT, Ur:IT f!0S.1 AND 2, CLOSE-0UT OF ITEllS II.F.1, ATTACHMENTS 1 A':D 2, OF fiUREG-0737 In our review of the Carolina Power & Light (CPLL) submittal of October 7, 1931, and of previous submittals, we took note of CP&L's provisions for autonatic diversion of Reactor Building Exhaust to the Standby Gas Treatment Systen, which discharges to the plant stack. 11e requested additional information from the licensee regarding ESF design criteria for initiating autoaatic diversion and also requested a cornitment for installation of a particulate and iodine sampler for the plant stack which would meet the criteria of f!UREG-0737, Item II.F.1, Attachaent 2.
In a response dated f. arch 31, 1932, and docketed April 2, 1982, the licensee states that he has determined that the requisite isolation signals for auto-matic diversion are designed and installed in accordance with ESF criteria.
ItisalsostatedthatCP&Lisdesigningasystemtogeinstalledintheplant vent which will have the capability of saapling to 10 uCi/cc for particulates and fodines; the schedule for installation of the iodine and particulate sampler is being reviewed and will be provided at a later date.
The l'.censee's submittal of f arch 31, 1982, is satisfactory to close-out our review of Items II.F.1, ' Attachments 1 and 2, for the Brunsuick Steam Electric Plant, Unit flos.1 and 2.
Our review has determined that the licensee satisfactorily meets the criteria of Items II.F.1, Attachments 1 and 2.
Origins 1 signed by R. Wayne Bousten R. llayne Houston, Assistant Director for Radiation Protection Division of Systems Integration cc:
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Dockets Nos. 50-269/270/287 f,; t.
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j Mr. William 0. Parker, Jr.
Vice President - Steam Production 5
Duke Power Company P. O. Box 33189 422 South Church Street Charlotte, North Carolina 28242 y
Dear Mr. Parker:
j A NRC Task Force on Pressurized Thermal Shock (PTS) recently visited 2
Robinson 2 to audit the adequacy of in-plant training programs and operating procedures with regard to PTS.
For your information and i
f guidance, a complete report of the audit and our letter to Carolina Power and Light Company is presented in the enclosure.
We intend to conduct a similar audit of your procedures and training with regard to PTS at~your Oconee Unit No.1 facility, and a team composed of Pacific Northwest Laboratory (PNL) personnel and the staff will visit the Oconee Unit No. I facility in the near future.
You will be contacted by your NRC Project Manager to arrange for this visit and he will be requesting infonnation relating to operating pro-
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cedures and training prior to the visits.
We request your cooperation hthis effort.
Sincerely,/
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Thomas M. Novak, Assistant Director i
for Operating Reactors Division of Licensing
Enclosure:
Audit Report 2
cc w/ enclosure:
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The SI pumps have a shut-off head of 1500 psig and have a rating of 375 gpm-at-1080 psig. The SI system also~contains three accumulators which discharge at 600 psig and two low head pumps (RHR) rated at 3000 gpm at 115 psig.
The Robinson 2 control room utilizes an L-shaped bench board which contains standard three-loop information.
However, most of the meters and controls are considerably smaller than other three-or four-loop control boards. The most important plant parameters are displayed on recorders which have a normal
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speed of 1 in/hr.
The following table contains the. major parameters available to an operator at Robinson 2 which would assist in monitoring PTS events:
Parameters Disolay RCS pressure Wide-and narrow range meters (1) wide-and narrow-range recorder RCS temperature,
Wide-range T and T meters and recorders for HOT COLD all_three loops Rx head thermocouple (1) meter - will be functional after refueling
. Core exit thermocouples Normal (Q) display using toggle switches _
Single T/C display Subcooling monitor Utilizes " pressure to saturation" meter May select core T/C or wide-range RTD Push-button selection may display *F subcooled in a digital form May select Loop AT.
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1 04/14/82 1-3 ROBINSON SER IHPUT SEC 1
Duke Power Company g.
cc w/ enclosure (s):
Mr. William L. Porter 3'
Duke Power Company P. O. Box 33189 422 South Church Street Office of Intergovernmental Relations Charlotte, North Carolina 28242 116 West Jones Street Oconee County Library 501 West Southbroad Street o
Walhalla, South Carolina 29691 Honorable James M. Phinney i
County Supervisor of Oconee County Walhalla, South Carolina 29621 Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission, Region II i
101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Regional Radiation Representative EPA Region IV 345 Courtland Street, N.E.
Atlanta, Georgia 30308 Hilliam T. Orders Senior Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 610 Seneca, South Carolina 29678 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Manager, LIS NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 J. Michael McGarry, III, Esq.
DeBevoise & Liberman 120017th Street, N.W.
Washington, D. C.
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g s.- [f Docket No. 50-261 Mr. J. A. Jones, Vice Chainnan Carolina Power and Light Company 336 Fayetteville Street Raleigh, North Carolina 27602
Dear Mr. Jones:
A NRC Task Force on Pressurized Thermal Shock (PTS) visited the Robinson 2 plant during April 5-7, 1982. The purpose of the visit was to audit the adequacy of in-place training programs and operating procedures with regard to PTS. The audit revealed that control room emergency procedures are apparently weighted toward core cooling and do not specifically concern PTS during certain events. The apparent procedural shortcomings could have been tempered by a strong ~ awareness of the PTS issue by plant personnel pending generic resolution of TMI Action Plan Item I.C.1 (Guidance for the Evaluation and Development of Procedures for Transients and Accidents).
The audit, however, apparently produced a varied response from good to poor. We feel that the varied responses were due to the need for closer-validation of training, by CP&L, of operator retention of the material covered in classroom training sessions regarding PTS.
A complete report of the audit is presented in the Enclosure. Sumaries of the interviews are contained in Section 3.3 and recommendations are addressed in Section 5.0 of the Enclosure.' Section 5 recommends that certain actions be accomplished prior to plant start-up.
It is our understanding, based on our phone conversation with your staff on April 20, 1982, that your response will be to accept the recommendations 1, 2, and 3 on page 5-1, with the qualification that item 1 will include three pertinent items mentioned in the report rather than "all available strip charts, etc." and recomendations 1 and 2 on page 5-2.
We understand that recommendation 3 will require a longer consideration due to the fact it should be coordinated with the Owners Group. We also understand that you will confinn this acceptance in a response dated April 27, 1982.
Sincerely, b
arm
. Thomas M. Novak, Assistant Director for Operating Reactors Division of Licensing
Enclosure:
As stated cc w/ enclosure:
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