ML032671259

Supplemental Information Pertaining to License Amendment Requests 02-06 and 02-07

ML032671259
Person / Time
Site:	Seabrook
Issue date:	09/15/2003
From:	Warner M Florida Power & Light Energy Seabrook
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NYN-03081
Download: ML032671259 (51)

Text

{{#Wiki_filter:FPL Energy Seabrook Station FPL Energy P.O. Box 300 Seabrook, NH 03874 Seabrook Station 1603) m-7000 SEP 5 2003 Docket No. 50-443 NYN-03081 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Seabrook Station Supplemental Information Pertaining to License Amendment Requests 02-06 and 02-07

References:

1. NYN-02089, "Changes to TS 3.9.4 Containment Building Penetrations," dated October 11, 2002

2. NYN-02103, "Revision to Technical Specifications Associated With Reduction of Decay Time for Core Offload," dated October 11, 2002

3. NYN-03043, "Revision to License Amendment Request 02-07, Changes TS 3.9.4 Containment Building Penetrations," dated May 30, 2003

4. NYN-03049, "Response to Request for Information Regarding License Amendment Requests 02-06 and 02-07," dated July 16, 2003

5. NYN-03054, "Response to Request for Information Regarding License Amendment Request 02-06," dated July 17, 2003

6. NYN-03066, "Supplemental Information Regarding License Amendment Requests 02-06 and 02-07," August 18, 2003

7. NYN-03077, "Response to Request for Information Regarding License Amendment Requests 02-06 and 02-07," dated September 9, 2003 By letter dated August 18, 2003 (Reference 6), FPL Energy Seabrook, LLC (FPLE Seabrook) identified that tracer gas testing of the Control Room Envelope (CRE) would be conducted during the week of August 25, 2003.

The results of this testing indicated that unfiltered inleakage to the CRE exceeds the current license basis limit. an FPL Group company

U. S. Nuclear Regulatory Commission NYN-03081 /Page 2 In response to Nuclear Regulatory Commission (NRC) staff reviews and questions pertaining to References 1 and 2, FPLE Seabrook commits to maintaining a program in effect to control the administration of potassium iodide (KI) to Control Room personnel during core alterations when the Primary Containment Equipment Hatch is open. This interim measure will remain in effect until the current license basis for unfiltered CRE leakage is revised. The PLE Seabrook commitment associated with this program is identified in Enclosure 3. By letter dated September 9, 2003 (Reference 7), FPLE Seabrook forwarded information to the NRC pertaining to the design of the Control Room Building Air (CBA) system west air intake and its compliance with the requirements of General Design Criterion 2 and 4 of Appendix A of 10 CFR 50. In a telephone conference conducted on September 11, 2003, the NRC requested FPLE Seabrook to forward two documents referenced in the response provided in Reference 7. The documents requested were YAEC Memo ESG 19/90 - "Tornado Missile Evaluation for Control Room West Air Intake Relocation," dated March 12, 1990 and YAEC Calculation SBC-367, Revision 1, "Control Room West Intake Relocation - Tornado Missiles, dated April 1990. The subject documents are provided in Enclosures 1 and 2 respectively. Should you have any questions concerning this response, please contact Mr. James M. Peschel, Regulatory Programs Manager, at (603) 773-7194. Very truly yours, FPL Energy Seabrook, LLC Mark E. Warner Site Vice President cc: H. J. Miller, NRC Region I Administrator V. Nerses, NRC Project Manager, Project Directorate 1-2 G. T. Dentel, NRC Senior Resident Inspector Mr. Bruce Cheney, Director New Hampshire Office of Emergency Management State Office Park South 107 Pleasant Street Concord, NH 03301

NYN-03081 Oath and Affirmation L Mark E. Warner, Site Vice President of FPL Energy Seabrook, LLC, hereby affirm that the information and statements contained within this document are based on facts and circumstances which are true and accurate to the best of my knowledge and belief Sworn and Subscribed before me this L*¢Lday of j~ £ htvb.#, 2003 1 Mark E. Warner

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Site Vice President f ~~Noad blic I~~~~~~~~~~~~~~~~~~~~ O EXPiRES E t~~~EPT.4,2007 i-E.'- to NYN-03081

k~!-1.1aM. t-a s2 -o9 ~ DCR 89-80 CA-0 ENCL4SURE F PAGE 5 MEMORANDUM YANKEE ATOMIC - BOLTON To DDl.^;i7ohnson Date March 12, 1990 Group # ESG 19/90 From G. A. Harper W.O.# 6124 Subject TORNADO MISSILE EVALUATION FOR CONTROL ROOM IM.S. # SB 0 01.16.03 WEST AIR INTAKE RELOCATION EXECUTIVE

SUMMARY

CLOSEOUT A probabilistic tornado missile impact evaluation was performed in support of the control room west air intake relocation. A conservative mean estimate of the annual probability of a tornado missile impacting te west air intake pipe is in the range of 2 x 10 to 3 x 10 per year. The NRC tornado missile acceptance criterion is that the probability of significant damage to a component foilowing a tornado missile strike be less than a mean value of 10 per year. This NRC acceptance criterion is met. Hardened tornado missile protection for the relocated west air intake is not necessary due to the acceptably low missile impact probabilities. BACKGROUND The control room west air intake is to be relocated adjacent to the east wall of the cooling tower. The Environmental Sciences Group (ESG) performed a probabilistic analysis of tornado missile impacts on the intake pipe. The analysis is based on information from the Seabrook Station site-specific tornado missile study (Reference 1). This study was reviewed and accepted by the NRC (see Section 3.5.2 of Reference 2). The west air intake analysis is documented in Reference 3 (see attachment). This analysis is similar to one that ESG performed in 1986 for the diesel generator exhaust stacks (Reference 4), which was reviewed and accepted by the NRC (Reference 5). DISCUSSION The NRC tornado missile acceptance criterion is: "The probability of significant damage to structure, systems and components required to prevent a release of radioactivity in excess of 10 CFR Part 100 following a missile strike, assuming loss of offeite power, shall be lesg than or equal to a median value of 10 or a mean value of 10 per year" (Reference 2).

DCR 89-80 CA-0 ENCLOSURE F PAGE 6 D. E. Johnson March 12, 1990 0 0 0 18 8 Page 2 West air intake tornado missile impact probabilities were estimated by adjusting impact probabilities from specific targets modeled in Reference 1 by ratios of target areas. The west air intake tornado missile target area was defined as the surface area of the above grade pipe plus 2.5 feet of the vertical buried pipe. The length of buried pipe was included to account for ground penetration of any tornado missiles. All horizontal portions of the underground intake pipe are at a sufficient depth to preclude a tornado missile related failure. The impact probabilities that were adjusted were conservatively chosen to account for the direction the target faces, target location and the number of potential tornado missiles in the surrounding area. This analysis is similar to the tornado missile evaluation for the diesel generator exhaust stacks (Reference 4). The NRC concurred that hardened protection of the diesel generator exhaust stacks was not necessary due to the acceptably low probability of tornado missile impact (Reference 5). The probability estimate is considered conservative for the reasons discussed in Reference 1 and the additional conservatisms applied in the calculation (Reference 3). CLOSEOUT RESULTS A conservative mean estimate of the annual probability of a tornado missile impacting the relocated west air intake pipe is in the range of 2 x 10 to 3 x 10 These probabilities are for missile impact. The probability that the pipe would be hit and sufficiently damaged to preclude performance of its intake function is lower than for impact alone. CONCLUSION The probability of a tornado missile impacting the relocated control room west air intake is less than the NRC acceptance criterion. Hardened tornado missile protection for the relocated west air intake is therefore not necessary due to the acceptably low tornado missile impact probabilities. George A. arpr Environmental Sciences Group GAH/lmf Attachment cc: W/o attachment J. G. Robinson J. P. Jacobson G. Tsouderos T. M. Cizauskas T. F. O'Hara

4 Ii~ 5 Z-1 10F J. 9 ] Co-DCR 89-80 CA-0 ENCLOSURE F PAGE 7 D. E. Johnson March 12, 1990 Page 3 REFERENCES 0001 89

1. Seabrook Nuclear Power Plant Tornado Missile Analysis, Applied Research Associates, Inc., Final Report C569, Revision 1, March 1984, Addendums 1 and 2, December 1984

2. NUREG-0896, Safety Evaluation Report Related to the Operation of Seabrook Station, Supplement No. 3, July 1985.

3. YAEC Calculation SBC-367, "Control Room West Intake Relocation Tornado Missiles,"

February 26, 1990.

4. Memorandum from G. A. Harper to R. E. White,

Subject:

Diesel Generator Exhaust Stacks - Tornado Missiles, ESG 46/86, April 24, 1986.

5. NUREG-0896, Safety Evaluation Report Related to the Operation of Seabrook Station, Supplement No. 5, July 1986.

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6'C0 I TABLE IV-2. ZONE DEFINITIONS I Coordinate Coordinate Zone Numbers Zone Numbers 1 17-33-44-45-17 11 11-12-14-13-11 2 25-24-23-22-25 12 15-14-17-16-15 3 21-20-19-18-21 23 1 3 1 4 33-27-32-31-30 14 4 6 4 5 28-34-33-32-28 15 5 9 5 6 29-28-27-26-29 16 8-17-45 7 39-36-35-40-39 17 48-45-46-47-48 8-36-37-38-35-36 18 52-50-49-47-52 9 41-39-43-42-41 19 51-1-49-50-51 10 7-. 3-12 7 20 53-51-50-52-53 I, .x, k-s, .......... -M j e X

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• -o TABLE IV-I.

SEABROOK STATION TRNAD= MISSILE ZONE COORDINATES Coordinate X V Poord1nate X V Nuber (ft) (ft) Number (ft) (ft) . i I 2 3 4 5 6 7 a 9 10 - 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 0 500 Sao So0 0 329 329 0 191 191 329 50o 329 500 392 392 500

• 00 675 675 500 500 590 590 500 731 992 100 100 293 293 675 675 293 1000 1000 675 463 463 769 769 769.

1000 1000 581 581 631 531 709 709 671 671 675 675 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 992 731 892 892 992 1092 1367 1074 1074 1524 1524 E52 852 500 SO 852 1038 500 844 0 0 0 -SQO -500 -1174 -2000 61i 611 675 looa 100C lOOC 611 612 161 136 611 19s 611 25C 386 386 1063 118E 222( 255C 175C 113C 113C 20C 164C 62( 3 3 3 3 )3

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p TL tV-SL-RTy O TALE IV-5. MISSILE DISTRIBIOR BY MtE ri w$~~~~~~~~~~~~~~~~~1 FIff" t SO en"Ipm 1 2 3 4 5 I I S I 10 t 12 .13 14 s11 II Is Is to tel 3 kw ttl O 100 0 too SW 0 T l.: 9SW ,*100 I n t "isd ins 5 Is 9 10 l a t0 SO Is I too IS sw 3 WTWA I0I 0o 9 tO 40 t0 5o0 is'0 0 IS 1.01 Ire 1.411 4 U1Int Uht tD 10 .10 10 is to m 4 tfly It 10 to 0 to u to 3-aPt, 1.0 t 2F 0 1 e le 4.16 3,60 6.92 I 9-fa 9P 160 se0 ISO mm au I.m a It-t l0 96 2 I so 30 14 400 96 ?5I 9 get..Un to 1r 44 n 3 54 4 I 10 320 nl S5 tO tw t Itis 4 20 4 2 4 £ 14 I 1 11 bo t3

• 40 60 III 2.00 4,90 I'm It m# sen t0 s0 2M0 120 W

10 300 40 As 40 390

2.

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101, IT2.

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JG ,P. 3r I .EDULE IF026 IF027 F028 -F029 _ 030 031 _ 032 N F033 .7 V.e. rsoa (Ss ,4/9 / o Pry) I ACCOROANCE WA C-203-86. SEE E007 I 3E --L ...., j ...3 N44 q T) C.. U-6 .1 % 4 I OC. fJo. gecoogo c5 a; &OL. K e Oya, - c-2 +2-3! 12-Il o AT-rAC WVAC/J I al Co14 ro( R o cakc 4 Tk 4 At~ l-ct oc L+4.,o I

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b/ t A TTACN MNT 3 s6( ,-3()77 .,> -7 TABLE 3.5-11 TORNADO-GENERATED MISSILES AND VELOCITIES FRACTI~O OF TOTAL TORNADO VELOCITY1 HORIZONTAL VELOCITY I REGION I (fPs) WESSILE, DESCRIPTION A. Wood plank, 4 weight 200 lb. Ins. 12 n. x 12 ft. 0.8 422 Z. Steel pipe, 3 In. diameter, echedule 40 10 ft. long, weight 78 lb. 0.4 211 C. Steel rod, I In. diameter 3 ft. long weight 8 lb. 0.6 317 D. Steel pipe, 6 n. diameter, schedule 40 15 ft. 10ng, weight 285 lb. 0.4 211 E. Steel pipe, 12 In. diameter, schedule 40 15 ft. ong, weight 743 lb. 0.4 211 T. Utility pole, 13-h ln. diameter, 35 ft. long, weight 1490 lb. 0.4 C. Automobile, frontal area 20 ft. 2 weight 4000 lb. 211 106 0.2 mhe maxim wind speed In Region is 360 =PM (528 fps) per Regulatory Guide 1.76, Design Basis Tornado for Nuclear Power Plants. I 1<.

A TA 6 qc CA, F/T Fe3 IV 3 EARTH-PENETRATING PROJECIILES 811 Jg (A) (XI)If ' (A lt 9

• s a..........

. a * &e***&{9** 12) A (W) M (W)h.... (13) The Velocity Effect, fg ).-Since most soils considered In this analysis are vertically homogeneous for only the top few feet, It ls not practical to hold the soil function constant over the complete range of velocities. The approach is to determine the velocity effect for the low-velocity range, during which the sollfunction may be assumed constant, and then separately determine the ve-locity effect for the high-velocity range. TABLE 3.-TARGET DESCRIPTION AND SOL CONSTANTS Target Test site soil descriptian DeptS, in feet Soil eonsbat I) I (2) (2) j (4) J (5) Claysy stlt, sty. densae hard. dry to a ,.2 To a e4 tr 2-I -t Mlain Dry Lake. Tonopah test 4 1-S-ad. aft" aese, dry. WOU eieXti a to 2S .9 Sand. ailt. Clayy. dense, drr tD daM 25 to at least 0 do 3 - a Clay. rty soft. aet brown a to is I A p. '4 4'. ,1p U 4 4 lalt trget aiMR, N1t. Clay. ait. very Stt sa with tranes of sd. hbhly mornmorilloatlue .6 to at least a 6_ I. 4

9.

4 Great Bat Lake Desert, Via Clay, sodt, Ct, grey, varved, MedLn to hi plasticity teo at lat i5 t 1V

orthrup Strip llSUIR Gypsite, selentte, hard,

noist, very homocensg" to at lest SO 2.5 X

4.15 t .6 4 .1 4-Gulkna Glater, Alas. be ghler O to at least to VI lielson, AFZ. Alas. 6Ut, claye7. frozen (permslroxt) 0 to at lst 30 9A ,<.f ( 0, a 4 re V gin zAr,. 5sd, lose to imedtum. oS t a to at least o VW TnOjAh tlesta' I. mYte a Ne Rock, Mls eded, fine. to at least 0 1 _ada test sMe graind aeomeraSe Dc Grants. Nt. Sandstone, tres hernnos e to at llst 30 Ii x CEwhf d Clayo Uty, w (bay iud) t atl i 40 )< X! Tewnpab test rar Sand, silty, ela, dense Idesert alluum e lat sst oo 4.4 _Dy"r_ aa. Clay. Moit, as a to at least is I e~ I Ta. I~~ I Fig. 4 shows a plot of velocity versus depth over the low-velocity range. The curve to best fit the data appears to be! (V) C In (1 + 2VI 10 "), for an impact velocity of less than 200 fps. he constant C is completely arbitrary. The main Dry Lake at Tonopah Test Range, Nevada, 16 a layered material Thus far in the analysis only the top 10 ft of the dry lake playa have been con-tidered. To determine the high-velocity effect, a preliminary set of soil con-stants was calculated and used to normalize the data to that used In the low-velocity part of the velocity effect function. Fig. 5 shows the normalized data and the curve representing the best data fit. In the final Iteration the high-velocityfunction appears tobe C. (V-100). The constant C4 must be determined St cj %. 4 C-

'e-t,e% I I.

S_ I i I R STI M.

808 may, 1969 S 7 &13 normalized (V. WA, and soil), any deviation In penetration performance when various nose shapes are used is an Indication of nose performance, The 6.0 Callber-Radius-Head (CRH) tangent ogive nose was selected as the standard on which penetration performance was based. The nose-shape effect, fJ (N), t8 is best described by a nose-performance coefficient which indicafes relative nose efficiency. The nose-performance coefficients were determined from Fig. I for the Ij tangent ogive nose shapes and for the flat noses. Additional nose-performance coefficients were determined from a series of tests during which all par.- meters were held constant except nose shape. Any variation n penetration jX performance (over an average of several tests) was then attributed to the nose effect, and aasln using the 6.0 CRH tangent ogive as the standard, nose-TAbLE L-NOSE-PERFORMANCE COEFFICIENTS Nose-perforznance Nose Shape coefficient, N (1) (2~~~~~~~~~~z).r Flat noe 0.,6 Tangent give, L2 Caliber Radlus Read (CR) 0.82 Tangent oglve 6.0 CR1 D.0i Tanent ogive, 9.25 CR! i. Tangent ogive, ILS CR1! 1.22 Cone, LID 2, where L Is length and D Is diameter LOB Con, LD

• I 2

Conic seb 1.28 lcice 1.31 Short Inverse ogive, LID I 2 1.03 Lag inverse ogive, LID

• 2 S.22

3. ~~~~~~

~~~t --S -~ ~ ~ ~ ~ ~~~*. Oatraruy ehasen as JV a &A.- Cone, plus cylinder, plus cone; with an over-all LID L C53ender conic nose tip. with a more abrupt conic base; with an over-all LID L-performance coefficients were calculated. The nose-performance coefficients obtained from Fig. I and frm the additional tests are presented n Table 2..2 Weight and Area Effect, fs (A) and fa (W).-The No. 279 series of tests (Table 1) was conducted under closely controlled conditions, including sim-Ilar soil conditions. It appears that sufficient data are available from this test series tojustifycombiningjt (A) and.W) into a single functionf ( WIA). For example, Fig. 2 is a plot of mpact velocity versus penetration distanee, with the soil and the ratio of weight-to-area held constant (the vehicle weight and area are varied in the same ratio.) It appears from the data fit that It Is reasonable to study the ratio of weight to area as a single function, and the crucial ustification for f, (A) Is In the fit of the test data to the final equation. jZCJ -c_ ,t7-I.

AT, tACH AA G (,. 9 f FORM WE-103-1 Revision 2 REVIEW FORM CALCULATION NO. SB Se<-3:(p S (0 t K S + o, TITLE: Co o N ( Rioei V W S ++/- 4 c IZ6 e TobeChecked + .orO icn to Cr To e heeked b orridner: fri El Is this a structural or mechanical analysis? If yes, was Table I check list used? Was a computer code used? If yes, was the code approved per WE-10? Was the code appropriate? Were outstanding SPRs evaluated? REIEE OEN .LESOLUTIQ .1 ( v ,4" afy= -_'t/4 ,>7r /.2 6p& '2-e 5 v2 v.A. fo 0z' r.H /C~~O S
'01.&('Q S-(
6t Pej I) 4, Al4d 4*-i-e 6a
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Reviewe / 6-> /t}/11 94 Date , 01 -I. t.i. -W j

I A TAc, i ' -l S Gc-1 7 p.40/ TABLE IV-4. SITE-SPECIFIC MISSILE ET CHARACTERISTICS final Weight-per Length/Depth Missile Aero Description eepth At U t e LengthLee Set Set (Typical) (in) (in) (lb/ftl Minimum Maxinun 1* 1 a Rebar l.00 0.79 2.67 36.0 36.0 2 1 c Gas Cylinder 10.02 9.45 38.64 4.0 10.0 3 1 d Drum, Tank 19.98 311.60 23.55 2.3 6.0 4* 2 b Utility Pole 13.50 143.10 32.06 31.1 31.1 5 2 c Cable Reel 42.21 126.60 140.70 0.5 0.6 6* 3 b 3' Pipe 3.50 2.20 7.58 34.3 34.3 7* 3 c 6' Pipe 6.63 5.60 18.90 27.2 27.2 8' 3 d 12' Pipe 12.75 14.60 42.60 14.1 14.1 9 5 b Eqpt., Bin 38.40 40.50 112.50 1.0 11.4 10 5 c. Dumpster 94.81 386.70 452.20 1.0 3.6 .11. 6 b Wood Tie 10.36 107.34 29.81 6.0 36.0 12* 9 a Wood Beam 12.00 48.00 9.50 12.0 12.0 13 11 a Wood Plank 12.00 12.00 3.30 8.0 12.0 14 12 a Metal Siding 48.00 24.00 25.00 2.0 4.0 15 13 a Plywood Sheet 48.00 50.74 15.02 2.0 2.0 16 14 b Wide Flange 11.29 8.16 27.87 8.0 60.0 17 15 a Angle Section 5.27 2.38 7.98 0.4 108.0 iB 16 a Channel Section 5.11 3.49 11.88 9.0 80.0 19 18 a Small Eqpt. 46.48 4.63 44.02 1.2 13.3 20 19 a Large Eqpt. 67.07 15.70 88.67 0.3 18.8 21 21 a Pipe Frame 53.69 1.61 13.95 1.1 6.0 22 22 a Grating 43.31 2.22 12.37 1.0 7.5 23 22 b Rect. Frame 97.41 11.00 47.23 1.0 5.0 24 22 c Crane Section 98.00 400.00 168.30 1.0 10.0 25 23 a Wood Frwme 168.00 240.00. 35.35 1.0 2.5 26* 25 a Vehicle 66.00 2574.00 250.00 2.9 2.9 .1

• Denotes membership in NRC standard spectrum of missiles [53:

Si rebar; Set 4 utility pole; Set 6 a 3-in steel pipe; Set 7 6 Set 8 12-in steel pipe; Set 12 a wood beam; Set 26 a vehicle. et I 1-in -in steel pipe; 4>vve,; 2 e a -S-cwc~c I IV-11

T A ) SC OF t I C T RS TABLE IV-17. PfATO Af SAMPLE STATISTICS OF tKtIM ELOCIT CARACTERISTICS 3b.2 Y.3att, Elipto)" fthtm Mr. veocity (q) lalif fo. V.1.ct (,) 2 PO a or sil If fti W t t st vltrodtst 1109 set tII (Ml sn (PO) tk.w Quertlit Etre fbooU 0431 n room Quentive txrte I itn.9 fd IS0 3010 46.S 26.6 235.6 121.4 2sk 233.3 51.2 t1.3 0-2 tility t. 20 300 44.0 59.6 3009 63 SS.I 91.s 230 26.2 35.1.i.. 3 3-3m. 919 1M0 300 1S0.2 23.1 249.3 141.0

3.

240.6 "1 5.l24 91.2 " 4 6-tm. PIP* I5 200 114. 143L.S 3.6 96.4 33.8 392.1 Se.3 6.t 83.3 L.- 5 12-t pi" tO 250 23.6 30.6 43.2 16.2 2me 40.6 16.2 11.9 22.3 6 3W 29.8 41.9 19.8 33.1 7?.2 16.3 38.5 24.5 J 33 teo M. 41.1 51.4 2".4 23.2 43.2 29.8 31.6 25.9 e 250 44.2 5.2 14.0 33.4 41.5 68.6 n.1 32.6 38.2 9 00 56.6 16.2 119.0 46.9 70.1 1IS. 2.A 33.5 41.6 IS0 50 66.9 I.6 70 24.0 35.9 50.8 1.9 6s. 66.6 1' 200 74.0 64.2 393.3

3.

58.9 81.2 61.2 65.? 72.0 i 250 6s.2 3L2 144.2 S.8 64.5 126.5 59.9 66.1 72.9 13 300 104.6 132.1 366.0 .3 119.4 114.8 S9.0 66.2 76.4 V 14 Tuic?, t0 200 24.3 32S 4.1 173 28.4 45.5 16.0 18.3 23.6 Is 250 33.1 49.9 103.9 26.6 47.4 3OS 16.2 1.6 25.4 i6 300 41.2 11.0 140.3 43.1 74.0 n36.9 17.2 22.6 43.6 1 rloPI 150 00 385.8 21.4 309 3L2D 216.0 2.32 5.9 102.4 M40.9 t. .0'0 3326t 313l based en 3,000 obfr~r itfe" for each *qIsItIt.nja t R Iw 9t.wItfldv'tt c wmo tI01 eatept tba PIu" 0001 M m arwtim m). S o ~ R -07e

1. t-eC 3-014 m

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. a% 1) , :.4 to NYN-03081

Commitments Associated With NYN-03081 Condition Report Commitment CR 03-07663 FPLE Seabrook commits to maintaining a program in effect to control the administration of potassium iodide (KI) to Control Room personnel during core alterations when the Primary Containment Equipment Hatch is open. This interim measure will remain in effect until the current license basis for unfiltered CRE leakage is revised.}}