ML17347A314
| ML17347A314 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 02/24/1987 |
| From: | Mcdonald D Office of Nuclear Reactor Regulation |
| To: | Woody C FLORIDA POWER & LIGHT CO. |
| References | |
| GL-83-28, GL-85-09, GL-85-9, TAC-52891, TAC-52892, TAC-53726, TAC-53727, TAC-55384, TAC-55385, NUDOCS 8703040381 | |
| Download: ML17347A314 (11) | |
Text
February 24/ l987 Docket Nos.
50-250 and 50-251 Mr. C. 0. Moody, Vice President Nuclear Energy Department Florida Power and Light Company Post Office Box 14000 Juno
- Beach, Florida 33408 DISTRIBUTION NRC PDR PD¹2 Reading TNovak OGC-Bethesda EJordan BGrimes JPartlow DHFT, NThompson DMcDonald DMiller ACRS (10)
Tech Branch
Dear Mr. Woody:
Subject:
Generic Letter 83 Request For Additional Information
Reference:
TAC Numbers
- 52891, 52892,
- 53726, 53727, 55384 and 55385 By letter dated November 8, 1983, you provided your response to Generic Letter (GL) 83-28, "Required Actions Based On Generic Implications of Salem ATWS Events."
Items 2. 1 (Part 1), "Equipment Classification (Reactor Trip System Components),"
2.2 (Part
- 1) "Fquipment Classification (Programs For All Safety Related Components),"
and 4.3 T.S. "Reactor Trip System Reliability, Technical Specification Changes" were responded to in your submittal.
The staff, with the assistance of our contractor, Idaho National Engineering Laboratory (EGIwG, Idaho) have reviewed your initial response to the above referenced items of GL 83-28.
We have determined that the additional information identified in the enclosure is needed to complete our review.
We request your response within 30 days from receipt of this letter.
The reporting and/or recordkeeping requirements of this letter affect fewer than 10 respondents; therefore OMB clearance is not required under PL 96-511.
Sincerely, Z;n E', H2>17ki~S I'age +n <<g~
J 2D ~Daniel McDonald, Jr., Project Manager PWR Project Directorate ¹2 Division of PWR Licensing-A Office of Nuclear Reactor Regulation
Enclosure:
as stated cc w/enclosure See next page L
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Mr. C. 0.
Woody Florida Power and Light Company Turkey Point Plant CC:
Harold F. Reis, Esquire Newman and Holtzinger, P.C.
1615 L Street, N.W.
Washington, DC 20036 Mr. Jack Shreve Office of the Public Counsel Room 4, Holland Buildinq Tallahassee, Florida 32304 Norman A. Coll, Esauire
- Steel, Hector and Davis 4000 Southeast Financial Center Miami, Florida 33131-2398 Mr. C.
M. Wethy, Vice President Turkey Point Nuclear Plant Florida Power and Light Company P.O.
Box 029100 Miami, Florida 33102 Mr. M. R. Stierheim County Manager of Metropolitan Dade County Miami, Florida 33130 Resident Inspector U.S. Nuclear Regulatory Commission Turkey Point Nuclear Generatina Station Post Office Box 57-1185 Miami, Florida 33257-1185 Mr. Allan Schubert, Manager Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Blvd.
Tallahassee, Florida 32301 Intergovernmental Coordination and Review Of+ice of Plannina 5 Budget Executive Office of the Governor The Capitol Building Tallahassee, Florida 32301 Administrator Department of Environmental Regulation Power Plant Sitinq Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Regional Administrator, Region IT U.S. Nuc1ear Regulatory Comission Suite 2900 101 Marietta Street Atlanta, Georgia 30373 Martin H. Hodder, Esquire 1131 NF., 86th Street Miami, Florida 33138 Joette Lorion 7269 SW, 54 Avenue Yiami, Flori da 33143 Mr. Chris J. Baker, Plant Manager Turkey Point Nuclear Plant Florida Power and Liqht Company P.O.
Box 029100 Miami, Florida 33102 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304
REOUEST FOR ADDITIONAL INFORMATION ITEM 2.1 (PART1),....
ERIC LETTER 83-28 EUP NT LSS TI N
ND ND NERFC
"(REACTOR RIP S
L SP C
CATI N CHANGES)"
TUR EY P
INT PL NT, NITS Review of the licensee's response dated November 8, 1983 for Items 2.1.(Part I),
2.2 (Part 2) and 4.3 T.S. of Generic Letter 83-28, discloses the need for additional information as follows:
A.
Item 2.1 (Part I) "E uipment Classification (Reactor Trip System Components)"
The licensee's submittal states that they have determined that components whose functioning is required to trip the reactor are included in systems which are treated as safety-related.
The submittal further indicates that the equipment classification at Turkey Point 3 and 4 is limited to the system level.
A program to increase the specif'icity of the. plant 0-List was said to be underway but no date was given for its completion.
Sub-sequent submittals have not provided additional information regarding progress.
Based on the review of the licensee's submittals, we find that at the time of the submittal the licensee had not identified the safety-related com-ponents of the reactor trip system.
The licensee needs to confirm that all components whose functioning is re-quired to trip the reactor are ~identified as safety-related on documents, procedures, and information handling systems used in the pl'ant to control safety-related activities, including maintenance, work orders. and parts replacement.
B.
Item 2.2 (Part I) "Equipment Classification (Proqrams For All Safet -Related Components)"
1.
Item 2.2.1 - Proqram The licensee's response does not confirm that all safety-related components are designated as safety-related on plant documents such as procedures, system descriptions, test and maintenance instructions, operating procedures, and in information handlinq systems so that personnel performing activities that affect such safety-related components are aware that they are working on safety-related com-ponents and are guided by safety-related procedures and constraints.
The licensee needs to state that their equipment classification con-forms to the above staff position.
If all safety-related components are not designated as safety-related on the relevant documents, the licensee should specifically describe the exceptions and provide a
,iustification for such exceptions for staff review.
Item 2.2. 1.2 - Information Handlin S stem The licensee's responses do not confirm that the information handling system includes a complete list of safety-related equipment and that procedures exist which govern its development and validation.
The licensee needs to make the above confirmation.
ts
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3.
Item 2.2.1.3 - Use of the F. uipment Classification Listing The licensee's response has not confirmed that criteria and procedures exist which govern, the use of the informatiori handling system to de-termine that an activity is safety-related and what procedures'for maintenance, surveillance, parts replacement and other activities defined in the introduction to 10 CFR 50, Appendix 8, apply to safety-related components.
The licensee needs to state that their program contains provisions to govern the use of the information handling to assure that a safety-related activity is identified as safety-related and that the proper procedures are selected and implemented.
4.
Item 2.2.1.5 - Desiqn Verification and Procurement The licensee's response does not confirm that their procurement specifications require that the appropriate design verification and qualification testing be provided by the supplier.
The licensee needs to state that their procurement specifications conform to the above staff position.
N
C.
Item 4.3 T.S. - Reactor Trip System Reliability, Technical Specification Chan es The licensee needs to sobmit proposed Technical Specification changes for the reactor trip logic and reactor trip breakers consistent with Generic Letter 85-09.
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