ML19256G405
| ML19256G405 | |
| Person / Time | |
|---|---|
| Issue date: | 12/05/1979 |
| From: | Triplett M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19256G395 | List: |
| References | |
| CON-FIN-A-3335, CON-FIN-A-3335-0 20-80-53, NUDOCS 7912310233 | |
| Download: ML19256G405 (9) | |
Text
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TRC FORM 173 u.s NUCLE AR REGULATORY COMMISSION CROE R NUMBE R 12 78) 20-80-53 OATE STANDARD ORDER FOR DOE WORK December 5, 1979 ISSUED TO: (DOE Offical ISSUED BY: INRC OffM:al ACCOUNTING CITATION APPRODRI ATION SYM eon.,
Brookhaven Area Office Office of Nuclear Reactor 31 X0200.200 Regulation u,,No..eR PERFORMING ORGANIZATION AND LOCATION 20 19 11 21 FIN NUM8eR Brookhaven National L'aboratory A3335 -0 WORK PERIOD THIS ORDER FIN TITLE FlxED C ESTIMATED E FROM:
TO:
Fire Protection Re-evaluation 10/1/79 9 /30/80 OBLIGATION AVAILABILITY PROVIDED BY:
A. THIS ORDER S
80,000 S.
TOTAL OF ORDERS PLACEO PRIOR TO THIS D ATE WITH THE PERFORMING ORGANIZ ATION UNCER THE SAME '*APPROPRI ATION SYMBOL" AND THE FIRST 50VR CIGITS OF THE S
1.370.000 1&R NUMe ga" C!TED ABOVE C. TOTAL ORCERS TO CATE (TOTAL A & 81 S
I 450,000 D. AMOUNT INCLUCED IN "C'* APPLICABLE TO THE " FIN NUMBE R" CITED IN THIS OR DE R.
S 80,000 FINANCIAL FLEX 181LITY:
[' AUTHORIZED.
FUNCS WILL NOT BE REPROGRAMMEO SETWEEN FINS. LINE O CONSTITUTES A LIMITATION ON OBLIGATIONS O FUNOS MAY BE REPROGRAMMED NOT TO EXCEED 210% OF FIN LEVEL UP TO S50K. LINE C CONSTITUTES A LIMITATION ON 08LIGATICNS AUTHORIZED.
STANDARD TERMS AND CONDITIONS PROV10ED DOE ARE CONSIDERED PART OF THIS ORDER UNLESS OTHERWISE NOTED.
ATTACHMENTS.
THE FOLLOWING ATTACHMENTS ARE HERESY SECURITY:
MADE A PART OF THIS ORDER:
C WORK ON THIS ORDER IS NOT CLASSIFIED.
M STATEMENT O F WOR K C WORK ON THIS OROER INVOLVES CLASSIFIED
[ ADQlTION AL TERMS AND CONDITIONS INFORMATION. NRC FORM 18715 ATTACHED.
After signature, please send a copy of this order to M. Paulette Triplett, NRR, P-428.
ISSUING AUTHORITY.
I ACCEPTING ORGANIZATION I
i signa tu R E
<J SIG N A T U R E l
M. 3aulette TriQlettf71,s),J,.gM ri.
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i Fiscal Assis ant NRC FORM 173 (2J8) 1657 292 3912310 9 3 3
SCOPE OF WORK Brookhaven National Laboratory (BNL) will provide technical assistance to the Division of Operating Reactors (DOR) in the area of fire protection. In particular, BNL will continue to assist in carrying out the Nuclear Regulatory Commission's (NRC) plan to re-evaluate the fire protection programs in operating nuclear power s ta tions. The two primary tasks of this project that BNL will participate in are discussed below.
TASK 1: ROUTINE (B&R 20 19 01 03)
A.
Plant Fire Protection Reviews BNL will complete the review of design descriptions for modifi-cations identified in the applicable Safety Evaluation Report's (SER's) Section 3.1 and to complete the evaluation of incomplete items identified in Section 3.2 and 3.3.
Those plants that arv, oc this time, identified as to requiring additional reviews are listed below.
TEAM 1 TEAM 2 TEAM 3 Indian Point 2 Haddam Neck Maine Yankee Indian Point 3 Dresden 1 Monticello Dresden 2/3 Prairie Island 1/2 Duane Arnold Peach Bottom 2/3 Millstone 1 Point Beach 1/2 Millstone 2 Surry 1/2 Quad Cities 1/2 San Onofre Turkey Point 3/4 Vemont Yankee Zion 1/2 Yankee Rowe TEAM 4 TEAM 5 Fi tzpatrick Beaver Valley Fort Calhoun Cooper Ginna Crystal River 3 H.B. Robinson Nine Mile Point Lacrosse St. Lucie 1 Pilgrim Three Mile Island 1 Three Mile Island 2 Calvert Cliffs 1/2 BNL's evaluation will be presented in a letter report 1657 20
. B.
On-Call Assistance BNL, as requested by the D0R staff, will evaluate specific fire protection issues as they are identified by the staff. The evaluation will be made in a timely manner and will address those selected issues that are of a current and high priority.
In general, Task 1B items will be, by definition, ranked as a secondary set of projects to the completion of Task 1 A plant reviews. Members of the BNL fire protection team, which has been in existence for the past three years, will remain on-call to the 00R staff for such issues related to the plant evaluations. In addition, other members of the Reactor Engineering Analysis Group with varied expertise may be utilized on specific problems. BNL's evaluation will be presented in a letter report.
At this point in time the following areas have been identified as the source of potential need for on-call assistance.
1.
Major Plant Modifications Fire protection issues associated with major plant modifications, other than those changes to meet fire protection goals, will be reviewed on a plant by plant basis. As licensees submit design changes for NRC approval, BNL will as requested review these modifications for their impact on the already approved level of fire protection at the specific plant. BNL will evaluate the fire protection adequacy during modification work and the fire protection changes deemed necessary as a result of the plant modifi-cation.
2.
Fire Protection Modifications After SER supplements for the ongoing plant evaluations are issued, BNL will review all plant submittals concerning a direct change to the previously agreed upon fire protection program.
3.
Hearings and Meetings BNL will provide assistance to discuss and defend positions taken in past evaluations of operating reactor fire protectionn capabilities at hearings and meetings.
1657 2%
. Task 2: OTHER GENERIC (B&R 20 19 11 21)
Throughout the 00R fire protection program there has been a need to establish general agreement on most significant generic fire protection issues. As the program continues, and generic issues become apparent, BNL will objectively review the subject matter and present the alternative solution to the. staff for final approval.
In each area, BNL will present to the staff the proposed methods which will be used to resolve the issue prior to beginning efforts on the task. BNL's evaluation of the generic issue will be presented in a letter report, unless othemise specified.
A.
In-Situ / Fire Detector Test Methods BNL will evaluate the proposed methods of determining optimum fire detector locaticns and fire detector operability. BNL will, where necessarf, perform independent analyses to verify models, correlations, and conclusions of each testing methodology.
There are four methods under consideration at present, (1) Nutech, (2) Jonnson, (3) Point Beach, and (4) Ft. Calhoun.
B.
Effect of Background Radiation in Fire Detection Systems Some smoke detectors are located in areas which may be subject to radiation fields above normal background. BNL will determine both (1) the nature of the effect of increasing radiation levels on smoke detectors, e.g., whether the detectors become more or les; sensitive, whether they move toward saturation; and (2) the level of radiation at which smoke detectors can no longer be considered reliable to detect smoke.
If increasing radiation levels are found to cause detector actuation, the effects of automatic suppression system actuation as a result of increased radiation levels will be evaluated.
C.
Research Succort SNL will aid the staff of DOR in the development, monitoring and modeling of required full-scale replication and separate effects fire tests to assure accuracy and validity of the test simulations relative to in-plant conditions. SNL will; assist in the develoo-ment of test procedures and configurations to guarantee that the test results are applicable to our evaluation of the plant.
Measurement schemes will be recommended to record the needed para-meters to analy:e the test results. Recommendations will be made for separate effects tests and model simulations to help define boundarf and initial conditions as well as to reduce the number 1657 295
- of dependent variables from the full-scale test. As required, BNL will develop the mathematical models to better understand the results of the experiment and its application to NRC fire protection guidelines. BNL will take part in witnessing tests performed at applicable facilities and attend pre-and post-test meetings. BNL will evaluate the test results and assess their effects on the plant evaluation.
D.
LER Evaluations BNL will evaluate fires or fire protection system / program failures reported (LER's) in nuclear power plants. When appropriate, recommendations will be cade to the 00R staff to improve current guidelines or to correct fire protection system deficiencies.
E.
Standards Succort BNL will aid in the updating of the BTP 9.5-1 Appendix A, Regulatorf Guide 1.120 and other governing fire protection documents.
F.
Flame Retardants BNL will evaluate current information (e.g., Sandia manufacturer, and licensee test results) to establish fire protection afforded by various flame retardant methods.
G.
Penetration Seal Qualification Tests BNL will compare test results for all plants to detennine whether differential pressure was present during the tests and provide evaluation of the significance of such pressure difference.
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SCHEDULE Task 1 - Routine Fire Protection Evaluations A.
Plant Fire Protection Reviews LICENSEE SUBMITTAL BNL EVALUATION PLANT COMPLETE RECEIVED
~~
TEAM 1 Indian Point 2 Indian Point 3 7/17/79 C TEAM 2 2.1 Haddam Neck 11/21/79 T 12/28/79 T 2.2 Dresden 1 11/16/79 T 12/21/79 T 2.3 Dresden 2/3 11/16/79 T 12/21/79 T 2.4 Duane Arnold 2.5 Millstone 1 11/21/79 T 12/28/79 T 2.6 Millstone 2 11/21/79 T 12/28/79 T 2.7 Quad Cities 1/2 2.8 San Onofre 1 12/14/79 T 1/21/80 T 2.9 Turkey Point 3/4 2.10 Vermont Yankee 2.11 Yankee Rowe 1/25/80 T 2/30/80 T 2.12 Zion 1/2 11/15/79 7 12/21/79 T TEAM 3 3.1 Maine Yankee 10/19/79 T 1/80 T 3.2 Monticello 10/80 T 11/80 T 3.3 Prairie Island 1/2 3.4 Peach 30ttom 2/3 3.5 Point Beach 1/2 3/15/80 T 4/22/80 T 3.6 Surry 1/2 5/ 81 7 6/81 T 1657 297
. LICENSEE SUBMITTAL BNL EVALUATION PLANT COMPLETE RECEIVED TEAM 4 4.1 Fitzpatrick 6/30/80 T 7/31/80 T 4.2 Ft. Calhoun ll/30/79T 2/22/80T 4.3 Ginna 12/31/79 T 1/31/80 T 4.4 H.B. Robinson 12/5/78 C 12/5/79 T 4.5 Lacrosse 6/30/80 T 8/15/80 T 4.6 Pilgrim 3/1/80 T 4/15/80 T 4.7 Three Mile Island 1 7/15/80 T 8/30/80 T 4.8 Three Mile Island 2 4.9 Calvert Cliffs 1/2 11/30/79 T 2/14/80 T TEAM 5 5.1 Seaver Valley 5.2 Cooper 5.3 Crystal River 3 5.4 Nine Mile Point 5.5 St. Lucie 1 6/80 T 7/80 T
- Not establisned.
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. B.
On-Call Assistance
( As requested) 1.
Major Plant Modification None identified at this time 2.
Fire Protection Modifications None identified at this time 3.
Hearings and Meetings 1.
Turkey Point 3/4 1657 299
LICENSEE SUBMITTAL Bhl EVALUATION COMPLETED RECEIVED Task 2: Other Generic A.
In-Situ Fire Test Methods 1.
Nutec Method 10/30/79 C 12/5/79 T 2.
Johnson Method 3.
Point Beach Method 4.
Ft. Calhoun Method 1/8/79 C 1/25/80 T 5.
Summary Report B.
Effect of Backcround Radiation in Fire Detection Systems 5/15/80 T C.
Research Succort
( As requested)
Research has not established schedule; however, BNL will meet schedule when established.
D.
LER Evaluations
( As requested)
None identified at this time E.
Standard Support
( As requested)
None identified at this time F.
Flame Retardants 3/15/80 T G.
Penetration Seal Qualification Tests 2/15/80 T 1(>S7 300