ML18026A301
| ML18026A301 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/03/1980 |
| From: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| PLA-503, NUDOCS 8007080240 | |
| Download: ML18026A301 (21) | |
Text
ns JL D
~
I cA re REGULA T INFORMATION DISTRIBUTION TEH (R IDS)
ACCESSION NBR:8007080240 DOC ~ DATE! 80/07/03 NOTARIZED:
NO DOCKET ¹ FACI e
Susquehanna Steam Electric Stationi Unit 1i Pennsylva 05000387 50 388 S
quehanna Steam Electric Station~
Unit 2~ Pennsylva 05000388 A
~
AUTHOR AFFILIATION CURT IS E N ~ > ~
Pennsylvania Power 8 Light Co, RECIP ~ NAHE RECIPIENT AFFII.IATION YOUNGBLOODPB ~ J.
Licensing Branch 1
SUBJECT:
Forwards marked up copy of FSARqSubsection 3.92 8 Table 3 '
33pcorrected to agree w/preoperational 8 startup tests program, Changes will be discussed at draft SER meeting during wk of Jul 14, DISTRIBUTION CODE:
BOO IS COPIES RECEIVEDtLTR ENCL I
SIZE:
TITLE> PSAR/PSAR AMDTS end Related Corr espondenoe NOTES;gZ'Alii Z s E J+S FSrl ACTION'EC IP IEINT COPIES IO CODE/'T1AHg LTTR ENCL AD 1
ICEAIS'/<V~
1 0
LA guS/I BRdoKIPl
~
1 0
REC IP IENT COPIES ID CODE/NAME LTTR ENCL BC qzu&CBCdd>, 8.
1 0
PH sn9gK,R 05 1
1 INTERNAL; A/0 CORE Il CS13 AUX SYS BR 18 CONT. SYS BR DIRE HUH FAC SFY EFF TR SYS BR ENV EIVG BR GEOSC IEN BR 09 IEC SYS BR 20 K IRK'00lOOD E R ~
29 MECH ENG BR NRC PDR 02 POKER SYS, BR QA BR 10 REAC SYS BR SIT ANAL BR 27 1
0 1
1 1
1 1
1 1
1 1
1 4
1 1
1 1
1 1
1 1
1 1
ACCID EVAL BR CHEM ENG BR CORE PERF BR 17 DIRECTOR NRR EHERG PREP 22'QUIP QUAL BR HYD/GEO BR 11 IEE oe HATL ENG BR HPA
'OELD PROC/TST REV BR SS BR12 REG FILE 01 ST BR 1
1 1
1 1
0 1
0 1
1 1
1 3
3 1
1 1
0 1
0 1
1 1
1 1
EXTERNAL; ACRS NSIC 30 04 10 10 1
1 LPDR 03 20 >980 TOTAL NUMBER OF COPIES REQUIREDe LTTR 51 ENCL 43
TWO NORTH NINTH STREET, ALLENTOWN, PA.
18101 PHONE:
(215) 821-5151 NORMAN W, CURTIS vice president Engineering 8 construction 821 5381 July 3, 1980 Docket Nos.
50-387 50-388 Mr. B. J.
Youngblood, Chief Licensing Branch No.
1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555 SUS(UEHANNA STEAM ELECTRIC STATION FSAR CHANGES ER 100450 FILE 841-1 PLA - 503
Dear Mr. Youngblood,
Attached is a marked up copy of FSAR Subsection 3.9.2 and Table 3.9-33 which have been corrected to agree with Susquehanna',s Preoperational and Startup Tests program.
He are planning to discuss these changes with you during the draft SER meeting the week of July 14.
If you have any questions, please call.
Very truly yours, N.
W, Curtis Attachment aoovoao Q,AIIO pool 5
I/(
PENNSYLVANIA POWER 8
LIGHT COMPANY
a qenerate loadinqs.
This analysis utilizes appropriate seismic floor response spectra and combines loads at "equencies up to 33 HZ in three directions.
Imposed stresses are qenerated and combined for normal, upset, and faulted conditions.
Stresses are
- compared, dependinq on the specific safety class of the equipment, to Industrial Codes, ASIDE, ANSI or Industrial Standards, AISC, al.lovables.
3.9.1 4.12 Seismic Cga~eor~ I Items Othe~than VASSS For statically applied loads, the stress allovables of Appendix F
of ~ASME Section III, Minter 1972 vere used for code components.
For noncode components, allovables vere based on tests or accepted standards consistent vith those in Appendix F of the code Dynamic loads fo" components loaded in the elastic range vere calculated using dynamic load factors, time history analysis, or any other method that assumes elastic behavior of the component.
The limits of the elastic ranqe are defined in Parag apn 1323 of Appendix F fo" the code components.
The local yielding due to stress concentration is assumed not to affect the validity of the assumptions of elastic behavior.
The stress allovables of Appendix F for elastically analyzed, components vere used for code components.
For noncode components, allovables vere based on tests or accepted material standards consistent vith those in Appendix F for elastically analyzed components.
The methods 'used in evaluating the pipe break effects are discussed in Section
- 3. 6.
- 3. 9. 2. la Preoperat ional Vibration and Dynamic Effects Testing on Pigin The test program is divided into three phases:, preoperational vibration, startup vibration, and operational transients.
3~9..1a 3
sr~no erat ional rib"ation Testing The purpose of the preoperational vibration test phase is to verify that operatinq vibrations in the recirculation amh~t m
'mr pipins a"e s'mar acceptable imam.
This phase oT t he test uses visual observation~
3 9-27
SSZS-PSAR urxnq s ea y s ate operation, vzsua o servatxon x.ndzcat tha bration is siqnificant, measurements will be made hand he ibroqraph.
Visual observations, manual an mote measurement ll be made during the following st state conditions:
a)
Recirc ulation s
minimum b)
Recirculation pumps of rated flov; c)
Recirculatio mps at 75% of flow; d)
Reci ation pumps at 100% of rated f RHR suction pipinq at 100'%f rated flov in the tdow coolinq mode.
3~9.2 a.2 Small Attach~ed i
i~m
~ sua o servatzon o
eac o
t e a
(a) throuq special attention vill be give attached. piping an ment connect nsure that they are not in resonance with t,
ation pump motors or flov induced vibrations.
peratin ion acceptance criteria ar t, appropriate corrective a 'llbe" t
- 3. 9.2. la~
S tart up Vibration The purpos~ef this phase of the program is to veri fy that the main steamy recirculation piping vibration are within acceptable limits.
Because of limited access due to hiqh radiation levels, no visual observation is made during this phase of the test.
Remote measurements shall be made during the follovinq steady state conditions:,
(a)
Main steam flow at 25% of rated; (b)
Main steam flow at 50% of rated; (c)
Main steam flow at 75% of rated; (d)
Main steam flow at 100% of rated; (e)
CIC turbine steam line at 100 (f)
RHR suc znq mode.
at 100%
o ov in the shutdown 3 9-28
SSES-FS AR 3 9. 2 la 4
Operating Tranaient Loafe The purpose of the operatinq transient test phase is to verify that. pipe stresses are within Code Limits.
The amplitude of displacements and number of cycles per transient of the main steam and recirculation pipinq vill be measured and the displacements compared vith acceptance criteria.
The deflections are correlated with the calculated deflections to assure that the stresses remain vithin Code limits.
Remote vibration and deflection measurements shall be taken during the follovinq transients.
a)
Recircula tion pump sta rts; b)
Recirculation pump trip at 100% of rated flov; Turbine stop valve closure at 100% pover; RZPZasa~raTtva Manual discharge of ~set S/R valve~at 1,000 psig and at planned transient tests that result in S/R valve discharge.
~92~a 5
9 at valnagron a~nkcc~etance Critegia The pipinq response to test conditions shall be considered acceptable if the organization responsible for the stress report reviews the test results and determines that the tests verify that the pipinq responded in a manner consistent vith the predictions of the st "ess report and/o" that the tests verify'hat piping stresses are vithin Code limits.
To insure test data integrity and test safety, criteria have been established to facilitate assessment of the test vhile it is in progress.
These criteria,'esiqnated Level 1 and 2, are described in the follovinq paragraphs.
3.9.2 la.5 1
Level 1 Cgit~eia Xf in the course of the tests, measurements indicate that the piping is respondinq in a mannner that would make test termination prudent, the test shall be termina ted.
Level 1
criteria establishes bounds on movement that, if exceeded, make a test hold or termination mandatory.
The limits on movement are based on maximum allovable Code stress limits.
3-9-29
SSES-PSAR seismic event by dynamic analysis only.
Piping systems having significant anticipated transients
- loads, caused by mai'n stop valve closure or relief valve blov for example, are analyzed for the time dependent forces.
In addition, piping steady state vibration and dynamic transient tests vill be performed. as summarized belov, to ensure that a)
Excessive steady state vibration is not present in the piping that would result in piping stresses and restraint loads above the allovables b)
The piping is adequately restrained to vithstaad the dynamic transient loads.
Cognizant design personnel familiar vith the systems to be tested vill develop the test
- plans, and evaluate the test results.
Also the cognizant design personnel vill vitness the test.
The data acquired from the tests vill be compared with the expected results to determine the acceptability of the total system response.
A list of all piping systems in the BOP is provided in Table 3.9-33.
ASXE Section III Class 1, 2 and 3 piping systens, high energy piping systems, moderate energy piping systems, seismic Category I and seismic Category II systems are identified in the Table.
The Table also id,entifies the
'ests to be performecd for each system Piping thermal expansion tests are performed for the safety-related piping systems vith normal cperating temperature exceeding 300 OP.
Safety related piping systems with normal operating tenperature less than 300 OP do not have significant thermal expansion to warrant thermal expansicn tests.
Engineering review of all seismic Cat'egory I piping systems including their supports, restraints or snubbers is performed after completion of construction and prior zo fuel load to ensure that no restraint of normal thermal movement occurs due to interferences and obstructions and that the support and restraints are in accordance with the design intent.
Por the systems receiving thermal expansion tests, the pipe movements are
-monitored to ensure that no restraint of normal thernal movement occurs at locations other than at the designed restraint locations.
The thermal expansion test program verifies that the free thermal expansion of piping systems take place at the snubbers by monitoring the thermal movement.
Perfcrnance of the snubbers designed for transient loads such as due to Main Stop Valve Closure or Hain Stean Belief Valve Discharge are verified by measuring the load in the snubber during the dynamic transient tests.
The snubbers are qualified by dynamic testing for cyclic loading as described in Subsection 3 9.3.0.1 Rev. 12, 9/79
- 3. 9m2
SSZS-PSAB Acceptance criteria for thermal expansion tests and dynamic transient tests is that the measured pipe displacements or restraint loads shall be below the calculated or design values.
57878 (g
Acceptance criteria for the steadypvibration tests is that the maximum measured amptitude of the piping vibration shall not induce a stress in the pipe more than the endurance limit of the material.
By limiting the maximum stress in the pipe due to steady state vibration below the endurance limit (allovable stress corresponding to 10'ycles or greater}, the steady state vibration induced stress vill not con tribute to the reduc tion of fatigue life of piping.
12 The Table 3.9-33 provides cross reference betveen the FSAR Section 3.9 and the appropriate test description in PSAR Chapter 14 3.9 2.1b 1 ~Pi in@ Dyuanic Transient Tests r~ eps~wgr~sl e~dgpr ~ +r ~sP During the the following piping dynamic transient tests vill be performed for the indicated modes oX operation.
4/PEA rc a)
Hain steam piping'outside the containment for main steam turbine stop valve ~ at 100 percent'oser PPrfe~f~
Pa j fi c'ff~h sa~4 I ro 7-ae euczcp OsaA'~~
BYPASS VA'>><~
b)
Hain steam bypass piping~for the turbine stop valve closure 5scsc 7'ED
-5 r~cZ~h.
c) g Hain steam safety/reLief 'valve dischazge piping for the main stean zelie f va lve pening,7 h'6 SC/EcfzO s)Pv S /scHF PdZ piped....
~ 8u. 7AZ SA'u'dcdArpds 8/P~<~.
d)
HPCZ tuzbine stean supply piping for HPCI turbine trip.
gzgcroz azs Pwr urS~gsgy~
Pisces RE Sweep Fee pm'?8'~8 Prom past experience, the dynamic transients in othez piping systems are no t sig nifica nt.
irpr e) 4'sadYe'-
Dynanic transient analysis of the subject linesghas been performed to determine the response of the piping system and the zestraint loads.
During the test the displacement of the pipe',
loads in the snubbers and restraints and pressure at representative locations Mill be measured.
Acceptance, criteria for this test are that the measured loads in the snubbers and restraints shall be below'he design values of the snubbers and restraints.
2n A+ Ctrl. (e) Sr ecc~p&~cc'.y /+>1~
. p>P +/r wesssrrrM rcfgrs~c-
~&/i 8=
les~ +Z~ W~c2ccgks/~
Rev.
12, 9/79, 3 9-32 a
SSES-PS AR
/~2 lb. 2 pi inc S~tead State Yibrat ion Testing The piping sy tern associated vith the followinq components'peration vill be observed foc steady state vibration during preoperational test proqcams or power ascension:
a)
RHR pump e)
Hain See~i~
b)
HPCI pump and turbine 4')
i=e>>4~m bs~
c)
Rc?c pump and turbine
) ~,i
~ Q
~/e>
d)
Core spray pump From experience on other nucleac power plants, the steady state vibration in other pipinq systems is not critical.
- However, abnormal vibrations of other systems during system valkdovn on initial startup oc povec escalation will be noted and instrumented if necessary to determine the acceptability of such vibration.
Steady state vibration in the sub ject piping systems is primarily induced by the flow in the pipe and the equipmeaz motion.
la
- qeneral, the specific causes of the steady state vibration is not knovn beforehand; therefore, desiqn enqiaeecs vith stress analysis experience and familiarity with the subject piping system vill visually observe the lines~du "ing all significant r
modes ot system operatTon and classr" y each line as acceptable iE the vibration is not siqaificant., or questionable if vibration is siqnificant.
The lines vith questionable steady sta e vibration vill be monitored by suitable instrumentation to determine the system response.
J
~
J t
inlay e~
~ big
~ <eS, d~ f4
'SMI +@4/e i
2 S ir di~e ey ia rra<
The type of the inst umentation, if necessary, will be determined by the design enqineer so that the maximum amplitude and frequency response of the piping system can be determined.
The instrumentation vill not screen out the significant frequencies.
For lines vith questionable steady state vibration, the acceptance criterion is that the maximum measured amplitude shall not induce a stress in the pipe more than the endurance limit of the material".
This is applicable to nucleac aad non-nuclear piping>>
When requiced, additional restraints will be provided to reduce the steady state vibcation and to keep the stresses below the accep ta nce criteria levels.
3 9-33
0 TABLE 3.9-33 BOP PIPING SYSTEMS POMER ASCENSION TESTING
~Pe e
2 Pi in S stem Code(s)/
S.C/)I.E H.E (1)
Thermal Dynamic Expansion Transient Tem
>200 F Test (2)
Test (3)
Steady
- State Vibration Test (O)
Remarks Process Sam lin Chlorination Com ressed Air 831.1 SC II H.E 831.1, SC II HE 831.1, SC II MF.
No N/A N/A N/A No N/A N A N/A No N/A N/A N/A Instrument Gas ASHE III-2,3 831.1, SC I SC II ME No N/A N/A N/A Feed Pump Turbine Stcam Makeup Mater 831.1, SC II II.E 831.1, SC II, HF.
Yes No N/A N/A N/A N/A N/A N/A Valve Stem Leakoff Acid Injection 831.1, SC II,
]IE 831.1, SC II HE Yes No N/A N/A N/A N/A N/A N/A
~ll dro en Stora e
Diesel Engine Auxiliaries HSIV Leakage Control 831.1, SC II HE ASHE III-3 831.1, SC I 6 II 1lF.
ASME III"122 831.1, SC I SC II IK No N/A Yes Yes g)
See Rema rks)
Yes N/A N/A N/A N/A N/A Emergency Diesel Exh Ilas T >300~F and Thermal Ex ansion Test Performed.
, N/A Reactor Recirc Motor / Generator lligh Pressure Coolant Injection Rev. l2, 9/79 831.1, SC II HF.
ASHE III-1,2 831.1, SC I SC II, H.E, HE No Yes N/A Yes Yes N/A HPCI Turbine Stop Valve Closure Transients for Steam Supply, Steady State Vibration for-Steam Supply Yes and Turbine Exhaust
@~pe. fr>>P ~ge+M SI'Ogre'+X Vlcr&J /~~
TABLE 3.9-33 BOP PIPING SYSTEMS POMER ASCENSION TESTING PlC>>/r/SCCC) l'~
Qlf>> 4F&
~ JCe.gp~a 3 S ICC l@~7 AW CJ'F'~ee 3
Pi in S stem
.actor Core Isolation rolin
.actor Mater
.ean up
.sidual lleat
.moval cleanup Filter mineralizer Code(s)/
S.C/H.E M.E (1)
ASME III-1,2 831.1, SC I SC II llE HE ASHE III-1,2 831.1, SC I SC Ilr lIE ME ASHE III-1,2r 3, 831.1, SC I a II, >mr HE ASME III-2 831.1, SC II ME Stead State Vibrati Test
(
Yes Yes N/A Yes Yes Yes N/A Yes Yes Yes N/A Yes (See Rema rks)
N/A N/A Thermal Dynamic Expansion Transient Tem
>200 F Test (2)
Test 3
Remarks teady State Vxbratx.on for Rk<CU-./team Supplv and Turbine Exhaust
~e'CJ'teady State Vibration for l831K,@lpne Inside Containment Majority of the System has Normal Operating Temperature less than 300 F Thermal Expansion Tests are done for SCI Systems MAA T >300'F.
Steady State Vibration for Inside Containment Piping and RllR Pump Dischare e.
control Rod Drive ASHE III"2 831.1, SC I SC TI lIE No N/A N/A N/A tandby Liquid Control ASHE III-1,2 831.1r SC I 5.
II, llE, HE No N/A N/A (See Rema rks)
N/A Only a small portion of the Line near RPV has Tem erature
>200 F ore Spray ASHE III"1,2 831.1, SC I 6 Il JIE HE Yes N/A Yes Steady State Vibration For Core Spray Pump Dischar e
.ev.
12'/79
1 O
TABLE 3.9 "33 BOP PIPING SYSTEMS POWER ASCENSION TESTING P~ae 4
Pi in S stem Fuel Pool Cooling, Cleanup 6 Dcmincralizer Code(s)/
S.C/((.E H.E (1)
ASME III-3 831.1; SC I SC II tfE Thermal Dynamic Expansion Transient Tem
>200 F Test (2)
Test (3
No N/A N/A Steady State Vibration Test (4
N/A Remarks Containmcnt Atmos hcric Control Solid Radwaste and Radwastc Solidification Off-Gas Rccombiner Ambi en t Temp e ra ture Charcoal Off-Gas Treatment Chilled Water ASHE III-2 831.1, SC I 6 II HE 831.1 SC II HE ASME III-3 831.1, SC I SC II
((.E 831.1, SC II HE ASHE III-3 831.1, SC I SC II HE No Yes No No N/A N/A N/A N/A N/A N/A N/A N/A N/A N A N/A Rev. 12, 9/79
TABLE 3. 9-33
~Pa e
5 NOTES (1)
Code(s):
ASME III Boiler and Pressure Vessel Code, -1, -2, or
-3 Denotes Nuclear Class 1,
2 or 3 Piping.
S.C I or II Denotes Seismic Category I or II Denotes High Energy Piping System i.e. Pressure
>215 PSI or Temperature
>200O During Normal Plant Operation.
M.E:
Denotes Moderate Energy Piping System (2)
(3)
'4)
(E>
Thermal Exoansion Tests for the indicated systems corresponds to test description ~-, Chapter 14.
s7- 'Q Dynamic Transient Tests. for the indicated systems corresponds to test description ~-, Chapter 14.
s7=5 I
Steady St libration Tests for the indicated systems corresponds to test description~-,
Chapter 14.
57= VO N/A - Denotes Not Applicable and it means test is not performed for the below reasons:
A)
For Thermal Expansion Rests:
The system is not safety-related or the normal operating temperature is less than 300oF B)
For Dynamic Transient Test:
The system is not safety-related or does not experience any significant transients.
C)
For steady State Vibration Tests; The system is not safety-related or no significant vibration expected.
f ~QCi~ara A o~ VI
+6'5+
Pi 4'g I 8 rrr roc~~
Rev. 12, P/79
gag Afeg C~
0 Cy 0
.r g
Vl0
/7
~O UNITED STATES NUCI EAR REGULATORY COMMISSION WASHINCTON, o. C. 20558 June 30, 1980 TO ALL APPLICANTS FOR CONSTRUCTION PERMITS, POWER REACTOR LICENSEES, ARCHITECT/ENGINEERS AND REACTOR VENDORS I am enclosing for your information a notice which has been forwarded to the Office of the Federal Register for publication.
This notice relates to regional meetings which will be held, beginning July 14, 1980, to address the portion of the Commission's Memorandum and Order dated May 23, 1980, which describes requirements pertaining to environmental qualification of electrical equipment installed in safety systems.
Sincerely,
Enclosure:
Notice cc w/encl:
Service Lists rrell G.
Division o
- senhut, Director icensing
I 1
7590-01 FEDERAL REGISTER NOTICE IMPLEMENTATION OF REQUIREMENTS FOR ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUlPMENT AGENCY:
U. S. Nuclear Regulatory Camnission ACTION:
NOTICE OF MEETING SUb9NRY:
On May 23,
- 1980, the NRC issued a Memorandum and Order that defines Canmission's requirements with respect to the environmental qualification of electricaI equipment at nuclear power plants.
In connection with these new requirements, the NRC will hold regional meetings to explain in more detail each of the require-ments.
Dates and Locations of Re ional Meetin s to be Held from 8:30 A.M. to 3:OO P.M.
July T4, 1980 - Region I Holiday Inn 26Q Goodard Boulevard King of Prussia, Pennsylvania July 15'980 - Region II
- Hyatt Regency Lancaster Roam 265 Peachtree Street',
N.E'.
Atlanta, Georgia July 16, 198Q - Region III July 1T, 1980 - Region IV A V Marriott O'Hare Motel 8535 W. Higgins Road Chicago, Illinois Holiday Inn North Irving, Texas
7590-61 FOR FURTHER INFORMATION CONTACT:
Robert A. Purple, Oiviskon of Licensing U.S. Nuclear Regulatory Cannissi on Washington, O.C.
20555 (Bol) ~92-7672.-
SUPPL~I'TAL INFORMATION:
The primary purpose. of these meetings will be to:
(1) provide a
more detailed technical explanation of the new NRC requirements; (2) provide
- a. description of the NRC approach,
- schedule, and administrative procedures to be followed in implenentfng these requirements; and (3) provide a forum for discussion of the requirements Persons, other than the NRC staff and licensee representatives.
may observe the proceedings.
but. wi11 be permitted to participate in the discussions.
only as time will'llow.
Registration of attendees wi11 be conducted prior to, each meeting at. the desi gnated locations.
Oated at, Bethesda Maryland, this 27 h day of June. 1980.
FOR T'riE NUCL~~
REGULATORY COfRISSION'rre G.
is rmu, rec or Division of Licensing Office of Nuclear Reactor Regulation
ALL POWER REACTOR LICENSEES Docket No. 50-348 Farley Unit 1
Docket Ho. 50-313 Arkansas Unit 1
Docket No. 50-368 Arkansas Unit 2 Docket No. 50-317 Calvert C1iffs Unit 1 Docket No. 50-318 Calvert Cliffs Unit 2 Docket No. 50-293 Pilgrim Unit 1
Docket No. 50-325 Brunswick Unit 1
Docket Ho. 50-324 Brunswick Unit 2 Docket No. 50-261 H. B. Robinson Unit 2 Docket No. 50-10 Dresden Unit 1 Docket No 50-237 Dresden Unit 2 Docket No. 50-249 Dresden Unit 3 Docket No. 50-Z54 guad-Cities Unit 1
Docket No. 50-265 squad-Cities Unit 2 Docket No. 50-295 Zion Unit 1
Docket Ho. 50-304 Zion Unit 2 Docket No. 50-213 Conn ticut Yankee (Haddam c.
Docket No. 50-3 Indian Point Unit 1
Docket No. 50-247 Indian Point Unit 2 Docket 50-286 Indian Point Unit 3 Docket No. 50-155 Big Rock Point Docket Ho. 50-255 Palisades Docket No. 50-409 Lacrosse Docket No. 50-Z69 Oconee Unit 1 Docket Ho. 50-270 Oconee Unit 2 Docket Ho. 50-287 Oconee Unit 3 Docket No. 50-334 Beaver Valley Unit 1'ocket No. 50-302 Crystal River 3 Docket Ho. 50-335 St., Lucie Unit 1
Docket No. 50-250 Turkey Point Unit 3 Docket No. 50-251 Turkey Point Unit 4 Docket No. 50-321 Edwin I. Hatch Unit 1 Docket No. 50-366 Edwin I. Hatch Unit 2 Docket No. 50-315 D. C. Cook Unit 1
Docket No. 50-316 D. C. Cook Unit 2 Docket No. 50-331 Ouane Arnold Docket No. 50-219 Oyster Creek Unit I Docket No. 50-309 Maine Yankee Docket No. 50-289 Three Mile Island Unit I Docket No. 50-320 Three Mile IsIand Unit 2 Docket No. 50-298 Cooper Station Docket No. 50-220 Nine Mile Point Unit I Docket No. 50-245 Millstone Unit I Docket No. 50-336 Millstone Unit 2 Docket No. 50-263 Monticello Docket No. 50-282 Prairie Island Unit I Docket No. 50-306 Prairie Island. Unit 2 Docket Ho. 50-285 Ft. Calhoun Docket No. 50-133 Humboldt Bay Docket No. 50-277 Peach Bottom 2 Docket No. 50-278 Peach Bottom 3 Docket No. 50-344 Trojan Docket No. 50-333 FitzPatrick Docket No. 50-267 Ft. St. Vrain Docket No. 50-272 Salem Unit I Docket No. 50-244 R., E. Ginna I Docket No. 50-312 Rancho Seco Docket No. 50-206 San Onofre I Docket No. 50-259 Browns Ferry Unit I Docket Ho. 50-260 Browns Ferry Unit 2 Docket No. 50-296 Browns Ferry Unit 3 Docket No. 50-346 Davis-Besse I
Docket No., 50-271 Vermont Yankee Docket No. 50-338 Horth Anna I Docket No. 50-280 Surry Unit I Docket No. 50-281 Surry Unit 2 Docket No. 50-266 Point Beach Unit I Docket No. 50-301 Point Beach Unit 2
Oocket Ho. 50-305 Kewaunee Oocket No. 50-29 Yankee-Rowe
Docket Ho. 50-'397 WPPSS I
Docket No. 50-460 WPPSS 2
Docket No. 50-508 WPPSS 4
Docket No. 50-513 Docket No. 50-509 MPPSS 3
WPPSS 5
Docket No.
STN 50-528 Palo Ver de I Docket Ho.
STN 50-529 Palo Verde 2
Docket Ho.
STH 50-530 Pal Verde 3
Docket No.
STN 50-553 Phipps Bend I Docket No.
STN 50-554 Phipps Bend 2
Docket No.
STN 50-566 Yellow Creek I Docket'o.
STN 50-567 Yellow Creek 2
Docket Ho. 50-467 Aliens Creek 2
Docket Ho. 50-437 Floating Nuclear Plant 1-8 Docket No. 50-488 Perkins I
Docket No. 50-489 Perkins 2
Docket No.
STN 50-556 Black Fox I Docket No.
STH 50-557 Black Fox 2 Docket No. 50-514
~ Pebble Springs I Docket Ho. 50-515 Pebble Springs 2
Docket No. 50-522 Skagit I Docket No. 50-523 Skagit 2 Docket No. 50-471 Pilgrim 2 Docket Ho. 50-412 Beaver Valley 2 Docket No. 50-413 Catawba I
Docket No. 50-414 Catawba 2
Docket No. 50-322 Shoreham Docket No. 50-275 Diablo Canyon I Docket No. 50-323 Diablo Canyon Z
Docket No. 50-461 Clinton I Docket Ho. 50-462 Clinton 2 Docket No. 50-416 Grand Gulf I Docket No. 50-417 Grand Gulf 2 Docket No. 50-354 Hope Creek I Docket No. 50-355 Hope Creek 2
Docket t/o. 50-311 Salem 2
Docket Ho. 50-458 Riverbend I
Docket No. 50-459 Riverbend 2
Docket Ho. 50-361 San Onofre 2
Docket No. 50-362 San Onofre 3
Docket No. 50-329 Midland I Docket No. 50-330 Midland 2 Docket No. 50-358 Zimmer I Docket No. 50-382 Waterford 3
Docket No. 50-390 Watts Bar I Docket No. 50-391 Watts Bar 2 Docket No. 50-424 Vogtle I Docket No. 50-425 Vogtle 2 Docket No. 50-483 Callaway I Docket No. 50-340 Seabrook Docket No. 50-327 Sequoyah I
Docket Ho. 50-328 Sequoyah 2
Docket STN 50-498 So. Tex-s I Docket STN 50-499 So. Texas 2
Docket No. 50-395 Summer I Docket No. 50-440 Perry I Docket No. 50-441 Perry 2
Docket No.50-35Z Limerick I Docket No. 50-353 Limerick 2 Docket STN 50-518 Hartsville I Docket STH 50-519 Hartsville 2 Docket STH 50-520 Hartsville 3 Docket STH 50-521 Hartsville 4 Docket No. 50-363 Forked River I Docket 50-341 Fermi 2
Docket Ho. 50-364 Farley 2
Docket No. 50-445 Comanche Peak I
Docket No. 50-446 Comanche Peak 2
Docket No. 50-491 Cherokee I
Docket No. 50-492 Cherokee 2
Docket Ho. 50-493 Cherokee 3
Docket No. 50-486 Callaway 2
Docket No. 50-339 North Anna 2
Docket No. 50-454 Byron I Docket No. 50-455 Byron 2 Docket Ho. 50-456 Braidwood I Docket Ho. 50-457
'raidwood 2
Docket No. 50-367 Bailly Docket t<o. 50-410 Nine Mile Point 2 Docket No. 50-546 Marble Hill I Docket No. 50-547 Marble Hill 2 Docket No. 50-400 Shearon Harris I Docket Ho. 50-401 Shearon Hart is 2
Docket No. 50-402.
Shearon Harris 3
Docket Ho. 50-403 Shearon Harris 4
Docket No. 50-373 LaSalle I Docket No. 50-374 LaSalle 2 Docket No. 50-389 St. Lucie Z
Docket No-. 50-482 Wolf Creek Docket No. 50-423 Millstone 3 Docket Ho. 50-438 Bellefonte I Docket No. 50-439 Bellefante 2
Docket Ho. 50-369 McGuire I Docket Ho. 50-370 McGuire 2
Docket No. 50-387 Susquehanna I
Docket Ho. 50-388 Susquehanna 2
0