ML19210A426

Tech Specs Change Request 19,Amend 2 to Amend DPR-50,App a Re Addl Restrictions to Ensure Hydraulic Snubber Reliability

ML19210A426
Person / Time
Site:	Three Mile Island
Issue date:	10/19/1976
From:	Arnold R METROPOLITAN EDISON CO.
To:
Shared Package
ML19210A419	List: ML19210A418 ML19210A426
References
NUDOCS 7910290645
Download: ML19210A426 (26)

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UNITED STATES OF A'IERICA

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NUCLEAR REGULATCRY CCMMISSION IN THE MATTER OF DOCKET 110. 50-289 LICE:iSE NO. DPR-50 METROPOLITAN EDISON COMPANY This is to certify that a copy of Technical Specification Change Request No.19, Arendment No. 2 to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with the U. S. Nuclear Regulatory Cc= mission and been served on the chief executives of Londonderry Township, Dauphin County, Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States mail, addressed as follows:

L'x. Weldon B. Arehart, Mr. Harry B. Reese, Jr.

Board of Supervisors of Board of County Commissioners Londonderr:, Township of Dauphin County R. D. #1, Geyers Church Road Lauphin County Court House Middletown, Pennsylvania 17057 Harrisbtrg, Pennsylvania 17120

EIROPOLITMI EDISON COMPMIY Ey Vice ? resident-Generation Dated: October 19. 1976

. 1 e S 3

1A69 e

1910299 S- g

s Three Mile Island Nuclear Station Unit 1 (TMI-1)

Operating License No. DPR-50 Dochet No. 50-289 Technical Seecification Chance Request No. 19. Amendment No. 2 The licensee requests that the enclosed pages be added to Appendix A of the TMI-l Technical Specifications Sectione 3 and h, as appropriate, and that Item 11, Page k-8 (Table h.1-2) be deleted from the existing Technical Specifications. Revised pages 11 and iii of Appendix A Table of Contents are also included. These pages replace those previously submitted by Change Request No. 19 on September 15,1976.

Reason for Proposed Change To reflect proposed revisicna to Change Request No.19 Amendment, as a result of the USNRC review of the subject request.

Safety Analysis Justifvine Change This proposed Technical Specification Change does not involve any unreviewed safety questions in that it only incorporates additional restrictions to ensure the reliability of hydraulic snubbers already in use at TMI-1. Note that on the grounds that those snubbers which are classified as "especially difficult to remove" are also difficult to properly inspect, the licensee disagrees with the proposed rewording of definition d, Section 3.16 (Bases).

Fifty-two of these " difficult" snubbers are located in the Reactor Building and present significant personnel safety hazards to an operator attempting to perform a proper inspection without scaffolding or ladders. Making this equipment available in the Reactor Building during operation is not practical in that containment integrity must be broken to allov ladders of significant length to be brought into the building. The time and additional radiation exposure nece. sary to erect and dismantle temporary scaffolding for each snubber locat;on in this category =akes this approach impractical for frequent inspection.

Twenty.three other snubbers are located in the vicinity of main stess lines and present additional personnel safety hazards to the inspector due to the proxit:d t of high te=perature piping during plant power operation. Therefore, the liceuee requests definition d. read as follows:

"d. Accessible during nor=al operation: Those snubbers that do not meet the criteria of paragraphs b. and c. above."

The licensee disagrees with the proposal to delete the last two paragraphs of Specification h.17.1. If a number of snubbers are found to be inoperable during an inspection due to a cause which can reasonably be construed as a generic problem, the decision to shutdown the reactor solely to inspect inaccessible snubbers vould be mede at the time of reportability. Adherence to an arbitrary periodic inspection interval may be unnecessary from a nuclear safety standpoint and has an unnecessarily harsh effect on plant operation. The licensee requests retaining the verding of Specification 4.16.1 as submitted in A=end=ent 1 to Change Request No. 19

\ 4, 69 v) 7E

TABLE OF CONTE:ES Section Pace 3.1.3 MINIMUM CONDITIONS FOR CRITICALITY 3-6 3 1.h REACTOR COOLANT SYSTE4 ACTIVITY 3-8 3.1.5 CHEMISTRY 3-10 3.1.6 LEAKAGE 3-12 3.1.7 MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY 3-16 3.1.8 SINGLE LOOP RESTRICTIONS 3-17 3.1 9 LOW POWER PHYSICS TESTING RESTRICTIONS 3-18 3.1.10 CONTROL ROD OPERATION 3-18a i 3.2 MAKEUP AND PURIFICATION AND CHEMICAL ADDITION SYSTE4S 3-19 i

3.3 EERGENCY CORE COOLING. REACTOR BUILDING EMERGEICY COOLING, AND REACTOR BUILDING SPRAY SYSTEMS 3-21 3.h TURBINE CYCLE 3-25 35 INSTRUMENTATION SYSTEMS 3-27 3 5.1 OPERATIONAL SAFETY INSTRUMENTATION 3-27

, 3.5.2 CONTROL ROD GROUP AND POWER DISTRIBUTION LIMITS 3-33 1 3.5.3 ENGINEERED SAFEGUARDS PROTECTION SYSTEM ACTUATION

! SETPOINTS 3-37 l 3.5.h INCORE INSTRUMENTATION 3-38 l 3.6 REACTOR BUILDEIG 3-h1 l 37 UNIT ELECTRICAL POWER SYSTE4 3-h2 3.8 FUEL IOADING AND REFUELING 3-kh 39 RADIOACTIVE MATERIALS 3 h6 3.10 MISCELLANECUS RADI0 ACTIVE MATERIALS SOURCES 3-h6 3.11 _HMTDLING OF IRRADIATED FUEL 3-55 3.12 REACTOR BUILDING POLAR CRANE 3-57 3.13 SECONDARY SYSTEM ACTIVITY 3-58 3.1h FLOOD 3-59 3.ri.1 PERIODIC INSPECTION OF THE DIKES AROUND TMI 3-59

.6.2 FLOOD CONDITION FOR PLACING THE UNIT IN HOT STANDBY 3-60 3.16 SHOCK SUPPRESSORS (SNUBBERS) h SURVEILLANCE STANDARDS h-1 h.1 OPERATICNAL SAFETY REVIEW h-1 8

k.2 REACTOR COOLANT SYSTE4 INSERVICE INSPECTION 4-11 h.3 TESTING FOLLOWING OPETING OF SYSTE4 h-28 h.h REACTOR BUILDING h-29 k.h.1 CONTAINMENT LEAKAGE TESTS h-29 h.h 2 STRUCTURAL DCEGRITY h-35 h.h.3 HYDROGEN PURGE SYSTE4 4-37 h5 DERGENCY LOADING SEQUENCE AND POWER TRANSFER, EMERGEICY CORE COOLING SYSTE4 AND REACTOR BUILDING COOLING SYSTEM PERIODIC TESTING h-39 h.5.1 E4ERGENCY LOADING SEQUENCE h-39 h.5.2 DIERGENCY CORE COOLING SYSTEM h h1 h.5 3 REACTOR BUILDING COOLING AND ISOLATION SYSTD1 k h3 h.5.h DECAY EEAT REMOVAL SYSTE4 LEAKAGE h-45 1A69 7

'hk g 11 4

4 TABLE OF CONTENTS Section Page k.6 E4ERGENCY POWER SYSTE4 PERIODIC TESTS h-h6 h.7 REACTOR CONTROL RCD SYSTE4 TESTS h h8 h.7 1 CONTROL R0D DRIVE SYSTE4 FUNCTIONAL TESTS h h8 h.7.2 CONTROL ROD PROGRAM VERIFICATION h-50 h.8 MAIN STEAM ISOLATION VALVES h-51 h.9 E4ERGENCY FEEDWATER PUMPS PERIODIC TESTING h-52 h.9 1 TEST h-5$

k.9 2 ACCEPTANCE CRITERIA k-52 h.10 REACTIVITY ANOMALIES h-53 4.11 SITE ENVIRONMENTAL RADI0 ACTIVITY SURVEY h-54 4.12 CONTROL ROOM FILTERING SYSTEM h-55 i

h.12.1 OPERATING TESTS h-55 l

h.12.2 FILTER TESTS k-55 i

h.13 RADI0 ACTIVE MATERIALS SOURCES SURVEILLANCE h-56 i h.1h REACTOR BUILDING PURGE EXHAUST SYSTE4 h-57 k.15 MAIN STEAM SYSTD4 INSERVICE INSPECTION h-58 h.17 SROCK SUPPRESSORS (SUUBBERS) f 5 DESIGN FEATURES 5-1 1

51 SITE 5-1 l 5.2 CONTARC4ENT 5-2 5 2.1 REACTOR BUILDING 5-2 1 5 2.2 REACTOR BUILDING ISOLATION SYSTE4 5-3 53 REACTOR 5h

' 5 3.1 REACTOR CORE 5h

5 3.2 REACTOR COOLANT SYSTD4 5-h 5.h NEW AND SPENT FUEL STORAGE FACILITIES 5-6

! 5.h.1 NEW FUEL STORAGE 5-6 5.h.2 SPETT FUEL STORAGE 5-6 55 AIR INTAKE TUNNEL FIRE PROTECTION SYSTEMS 5-8 6 ADMINISTRATIVE CONTROLS 6-1 6.1 RESPCNSIBILITY 6-1

, 6.2 ORGANIZATION 6-2 6.2.1 0FFSITE 6-2 6.2.2 FACILITY STAFF 6-2 6.3 STATION STAFF QUALIFICATIONS 6-3 6.h TRAINING 6-3 6.5 REVIEW AND AUDIT 6-3 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC) 6-3 6.5 2.A MET-ED CCRPORATE TECHNICAL SUPPORT STAFF 6-5 6.5 2.3 GENERAL OFFICE REVIEW BCARD (GORB) 6-7 6.6 REPORTABLE OCCURRENCE ACTION 6-10 6.7 OCCURRE;CES INVOLVING A SAFETY LI'4IT VIOLATION 6-10a 6.8 PROCEDURES 6-11 i

I. iii iA69 255 i

3 16 Shock Superessors (Snubbers)

Apelicability Applies to the operability of the hydraulic snubbers listed in Table 3.16.1.

Objective To identify those conditions for which the operability of the hydraulic anubbers are required and to identify the time limits in which either the snubber must be =ade operable or reactor shutdovn must occur. -

Specification 3.16.1 During all modes of operation except Cold Shutdown and Refueling, all safety-related hydraulic snubbers listed in Table 3 16.1 shall be operable except as noted in 3.16.2 through 3.16.4 below.

3.16.2 From and after the time that a hydraulic snubber is determined to be inoperable, continued reactor operation is per=issible only during the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless the snubber is sooner

=ade operable.

3.16.3 If the require =ents of 3.16.1 and 3.16.2 cannot be =et, an orderly shutdown shall be initiated and the reactor shall be in cold shutdown condition within an additional 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

3.16.h If a hydraulic snubber is determined to be inoperable while the reactor is in the shutdown or refuel mode, the snubber shall be =ade operable prior to reactor start-ap.

3.16.5 Snubbers =ay be added to safety-related systems without prior License A=endment to Table 3.16.1 provided that a revision to Table 3.16.1 is included with the next License Amendment Request.

Bases Snubbers are designed to prevent unrestrained pipe =otion under dynamic loads as night occur during an earthquake or severe transient, while allowing nor=al ther=al =otion during startup and shutdown. The consequence of an inoperable snubber is an increase in the probability of structural dacage to piping as a result of a seismic or other event initiating dynamic loads. It is, therefore, required that all hydraulic snubbers required to protect the primary coolant system or any other safety system or ce=ponent be operable during reactor operation or other pericds when severe transients =ight cause damaging dynamic leads.

1469 256

f l

Because the snubber protection is required only during relatively low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repairs or replacements. In case a shutdown is required, the allowance of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reach a cold shutdown condition vill permit an orderly shutdown consistent with standard operating procedures.

Since plant startup should not co=rence with safety equipment having known defects, specification 3.16.h prohibits startup with inoperable snubbers.

Table 3.16.1 lists all hydraulic snubbers installed on nuclear safety related systems throughout the plant. Snubbers were classified for '

the table in accordance with the following guidelines:

a. High Radiation Area During Shutdown: Those snubbers located in a general field of greater than 100 mr/hr, during shutdown.

L. Especially difficult to re=ove: Those snubbers that are elevated more than 10 feet off the floor and that, due to interferences ,

may not be safely reached from a suitable work platform,

c. Inaccessible during nor=al operation: Those snubbers that are located within an area where the general field is 100 mr/hr. or greater during nor=al operation.

d. Accessible during nor=al operation: Those snubbers that do not meet the criteria of paragraphs b and c above.

i469 257

TABLE 3.16.1 SAFETY BELATED HYDRAULIC SNUBBERS Snubber in Snubber Snubbers Snubbers High Radiation Especially Inaccessible Accessible Snubber . Area During Difficult During Normal During Normal Shutdown" MK.No. Location Elevation To Remove Operation Operation R.B. Inside Sec. Shield RC-h 355 Ho Yes Yes No N.E. Quad.

x. dg. nside Sec. Shield RC-5 .

N.E. Quad. Top of PZR Near RC-V3 355 No No Yes No -

Itx. Bldg. Inside Sec. Shield RC-15 N.E. Quad. Top of PZR Near RC-V3 355 No Yes No No Rx. Bldg. Inside Sec. Shield RC-16 355 No Yes No N.E. Quad. Top of PZR Near RC-V3 No Rx. Bldg. Inside Sec. Shield RC-17 355 No Yes No H.E. Quad. Near RC-V1 No Ex. Bldg. Inside Sec. Shield RC-18 355 No No Yes No N.E. Quad. Near Rt-V1 Rx. Bldg. Inside Sec. Shield RC-19 355 N0 No Yes No N.E. Quad. Near RC-V1

. Bldg. Inside Sec. Shield RC-23 355 No No Yes No N.E. Quad. Near RC-V1 Hx. dg. InsMe Sec. NeM RC-20 353 No Yes No N.E. Quad. No RC-21

x. g. nsMe Sec. Shield N.E. Quad. 353 No No Yes No

• • 8' "81 *

• RC-22 353 No No Yes No

. N.E.. Quad.

dg. naide Sec. Shield RC-9 N.E. Quad. Near RC-V31 Rx. Bldg. Inside Sec. Shield 3h6 No No Yes No h RC-7 353 No No Yes No N.E. Quad. Near RC-V31 Rx. Bldg. Inside Sec. Shield RC-8 353 No No Yes No N.E. Quad. Near RC-V31

. x Bldg. Inside Sec. Shield RC-6 353 No No Yes N; 3 N.E. Quad.

Mx. Bldg. Inside Sec. Shield RC-lO & 346 No Yes W N.E. Quad. NO No Ex. Bldg. Inside Sec. Shield RC-ll N 328 No No Yes No N.E. Quad. ,

1nside Sec. Shield RC-12 328 No No Yes No

m_ .

TABLE 3.16.1 SAFETY RELATED HYDRAULIC SNUBBERS l SmWaer In Snubber Snubbers Snubbers High Radiation Especially Inaccessible Accessible Area During Difficult During Normal During Normal Snubber MK No. Incation Elevation Shutdown" '

To Remove Operation Operation

x. Bldg. Inside Sec. Shield Yes No RC-13 321 No No N.E. Quad.

Rx. Bldg. Inside Sec. Shield Yes No RC-lh ,

N.E. Quad 321 No No

. Inside Se . Shield Yes No MUE-38 N},B g g 318 No No MUE-39 Rx. B d Inside Sec. Shield 318 No No Yes No @

Rx. Bldg. Inside Sec. Shield Yes No PR-23 3h0 No No N.E. Quad. RC-RV-1A Disch. Line Rx. Bldg. Inside Sec. Shield No Yes No PR-2h 340 NO N.E. Quad. RC-RV-1A Disch. Line Rx. Bldg. Inside Sec. Shield Yes No PR-25 3h0 N No N.E. Quad. RC-RV-1B Disch. Line Rx. Bldg. Inside Sec. Shield No Yes No PR-26 340 NO N.E. Quad. RC-RV-1B Disch. Line Rx. Bldg. Inside Sec. Shield Yes No PR-34 345 NO Ho N.E. Quad. RC-RV-1A Disch. Line Ex. Bldg. Inside Sec. Shield No Yes No PR-36 345 NO N.E. Quad. RC-RV-1A Disch. Line

h. Bldg. Inside Sec. Shield No Yes No PR-35 3h5 No N.E. Quad. RC-RV-1B Disch. Line Ex. Bldg. Inside Sec. Shield

~

N.E. Quad. RC-RV-1B Disch. Line 345 No No Yes No g

Rx. Bldg. Inside Sec. Shield pg_g7 355 No No Yes No N.E. Quad. RC-HV-2 Disch. Line

. g. ns e. hield PR-48 355 No No Yes No

__. N.E. Quad. RC-RV-2 Disch. Line USE-77,4 Rx. Bldg. Inside Sec. Shield 333 No No Yes No Os N.E. Quad.

Rx. Bldg. Inside Sec. Shield NSE-78 334 No No Yes No N.E. Quad.

Ex. Bldg. Inside Sec. Shield USE-Th 331 No No Yes No

_, N.E. Quad.

~

Rx, Bldg. Inside Sec. Shield NSE-75 332 No No Yes No H.E. Quad.

O

TABLE 3.16.1

BAFETY RELATED HYDRAULIC SNUBBERS Snubber In Snubber Snubbers Snubbers High Radiation Especially Inaccessible Accessible Snubber Area During Difficult During Normal During Normal MK No. Incation Elevation Shutdown

• To Remove Operation Operation NSE-76 Rx. Bldg. Inside Sec. Shield 332 No No Yes No l N.E. Quad.

! x. Idg. Imide Sec. Shield NSE-103, 334 No No Yes No N.E. Quad.

NSE-104

x. g. nsi e ec. hield No Yes No 33h No N.E. Quad.

NSE-105

x. ldg. Inside Sec. Shield N.E. Quad.

33h No No Yes No h

x. ldg. InsMe Sec. SMeld Yes NSE-lO8 33h No No No N.E. Quad.

Rx. Bldg. Inside Sec. Shield NSE-110 331 No No Yes No N.E. Quad.

Rx. Bldg. Inside Sec. Shield NSE-ll2 332 No No Yes No N.E. Quad. _

Rx. Bldg. Inside Sec. Shield NSE-ll3 N.E. Quad.

338 No No Yes No Ex. Bldg. Inside Sec. Shield MS-201 338 No Yes Yes No N.E. Quad.

Rx. Bldg. Inside Sec. Shield NSE-80 332 No No Yes No S.E. Quad.

NSE-81

• • 8* "8

• I 331 No Yes No No S.E. Quad.

Rx. N g. Inside Sec. SMeld NSE 82 331 No Yes No S.E. Quad.

Ex. Bldg. Inside Se . Shield No Yes k

NSE-96 338 No No No S.E. Quad.

Ex. Bldg. Inside bec. Shield NSE-96A 338 No No Yes No S.E. Qud.

~ ** 8* "8I *

• I No NSE-151 -c 334 No Yes No S.E. Quad.

• • 8* "81

• h1 No Yes NSE-153 M 331 No No

)

S.E. Quad.

Rx. Bldg. Inside Sec. Shield EF-ll6 N) , S.E. Quad.

330 gO No Yes No Ex. Bldg. Inside SecJ Shield FW-109 6 S.E. Quad. 325 No Yes Yes No

TABLE 3.16.1 SAFETY RELATED HYDRAULIC SNUBBERS i

Snubber In Snubber Snubbers Snubbers High Radiation Espec' ally Inaccessible Accessible Snubber Area During Difficult During Normal During Normal MK No. Location Elevation Shutdown

• To Remove Operation Operation Rx. Bldg. Inside Sec. Shield

• W-110 325 No Yes Yes No S.E. Quad.

Inside Sec. Shield MUE-20 , 315 go No Yes No

h. Bldg. Inside Se . Shield MUE-69 310 Yes Yes No S.E. Quad. No Rx. Bldg. Inside Sec. Shield NSE-85 332 Yes Yes No N.W. Quad. No Ex. Bldg. Inside Sec. Shield NSE-86 331 Yes Yes No N.W. Quad. No Inside Sec. Shield Yes Yes No USE-87 g ,

331 p, Ex. Bldg. Inside Sec. Shield NSE-88 334 Yes Yes No ,

N.W. Que.d. No

• • AdE* "*'d ** d No Yes No NSE-131 33h N.W. Quad. No

h. Bldg. Inside Sec. SMeld NSE-132 334 No No Yes No N.W. Quad.

NSE-133

• • d8' "81 **

33h No Yes No N.W. Quad. NO

h. Bldg. Inside Sec. Shield USE-138 331 NO Yes Yes No N.W. Quad.

Rx. Bldg. Inside Sec. Shield NSE-lbl 331 No No Yes No N.W. Quad.

Rx. Bldg. Inside Sec. Shield HSE-lh2 331 gO No Yes No H.W. Quad.

Rx. Bldg. Inside Sec. Shield MUE-43 310 y0 No Yes -

No N.W. Quad.

19fE-4h Ex. Bldg. Inside Sec. Shield 3 310 No No Yes No N.W. Quad.

Rx. Bldg. Inside Sec. Shield h2 -- -Ih N.W. Quad.

310 No No Yes No Rx. Bldg. Inside Sec. Shield 0F46 310 No No Yes No N.W. Quad.

x. ldg. Inside Sec. Shield CF-16A r J N.W. Quad.

316 No No Yes No cy

TABLE 3.16.1 SAFETY RELATED IIYDRAULIC SNUBBERS Snubbac In Snubber Snubbers Snubbers liigh Radiation Especially Inaccessible Accessible Snubber . Area During Difficult During Normal During Formal MK No. Incation Elevation Shutdown" To Remove Operation Operation NSE-89 Ex. Bldg. Inside Sec. Shield Yes No 334 No No S.W. Quad.

Rx. Bldg. Inside Sec. Shield Yes No NSE-90 , 334 No No -

S.W. Quad.

Rx. Bldg. Inside Sec. SMeld No Yes No NSE-91 334 No S.W. Quad.

Inside Sec. SMeld Yes' NSE-92 "$,B g ,

334 No No No -

Hx. Bldg. Inside Sec. Shield No Yes No NSE-122 342 No S.W. Quad.

Rx. Bldg. Inside Se . Shield No Yes No NSE-129 334 No S.W. Quad.

h. Bldg. Inside Sec. SMeld No Yes No NSE-130 33h No S.W. Quad.

g_gg Ex. Bldg. Inside Sec. Shield No Yes No 325 No S.W. Quad.

Ex. Bldg. Inside Sec. Shield No Yes No FW-ll5 S.W. Quad.

325 No

x. Idg. Inside Sec. Shield Yes Yes No EF-113 320 No S.W. Quad.

x. Bldg. Inside Sec. Shield Yes Yes No DH-4 302 No o.W. Quad.

x. ldg. Inside Sec. Shield Yes Yes No Dil-5 302 No S.W. Quad.

Ex. Bldg. Incide Sec. Shield No Yes No CF-6 316 No S.W. Quad.

• • 3108' U" "id" 8

• 8 1"Id 340 No No Yes Dil-32 No N.E. Quad.

Rx. Bldg. Outside Sec. Shield Yes MS-202 337 No No No N.E. Quad.

Ex. Bldg. Outiside Sec. Shield No MS-203 -'* N.E. Quad. 337 No Yes No MS-206 }] Ex. Bldg. Outside Sec. Shield 337 No Yes No No N.E. Quad.

N Rx. Bldg. Outside Sec. Shield 337 No Yes No No MS-207 a- N.E. Quad.

N

TABLE 3.16.1 SAFETY RELATED HYDRAULIC SNUBBERS I Snubber In Snubber Snubbers Snubbers Righ Radiation Especially Inaccessible Accessible Snubber Area During Difficult During Normal During Normal MK No. Location Elevation Shutdown

• To Remove Operation Operation Rx. Bldg. Outside Sec. Shield No Yes No No 337 N.E. Quad.

MS-286 , Rx. Bldg. Outside Sec. Shield No Yes No No 337 N.E. Quad.

Rx. Bldg. Outside Sec. Shield No Yes No No PR48 326 N.E. Quad.

Rx. Bldg. Outsid Se . hield No Yes No No PR-39 326 N.E. Quad.

. Bldg. Outside Sec. Shield No Yes No No PR 10 4 326 N.E. Quad.

PR bl

x. 8. Outside Sec. SMeld 326 No Yes No No N.E. Quad.

• • 8' "8 * *

• Yes No No PR 12 4 326 No N.E. Quad.

. B dg. Outside Sec. m eld No Yes No No PR-43 326 N.E. Quad.

Rx. Bldg. Outside Sec. Shield No No No Yes PR4h 309 N.E. Quad.

Rx. g. utside Sec. N eld No No No Yes PR-45 309 N.E. Quad.

Rx. Bldg. Outside Sec. Shield No No No Yes PR-h6 309 N.E. Quad.

. ldg. Oatside Sec. Meld No Yes No No PR-49 326 .

N.E. Quad.

Ex. Bldg. Outside Sec. Shield No Yes No No PR-50 326 N.E. Quad.

. dg. Outside Sec. Shield No No -

Yes CF-14 309 No N.E. Quad.

Rx. Bldg. Outside Sec. Shield No No No Yes CF-15 300 N.E. Quad.

Rx. Bldg. Outside Sec. Shield No Yes No No FG-200 _ 338 S.E. Quad.

Rx. Bldg. Outside Sec. Shield No Yes No No FE-204 338

, , S.E. Quad.

0utside Sec. Shield No Yes No No MS-205 g 338 2 .

U

m . __ _. ._

TABLE 3.16.1 SAFETY REIATED HYDRAULIC SNUBBERS Snubber In Snubber Snubbers Snubbers Iligh Radiation Especially Inaccessible Accessible Snubber Area During Difficult During Normal During Normal MK No. Location Elevation Shutdown

• To Remove Operation Operation MS-291 Rx. Bldg. Outside Sec. Shield No 338 No Yes No S.E. Quad.

Rx. Bldg. Outside Sec. Shield No BS-27 ,

341 No Yes No -

S.W. Quad.

Rx. Bldg. Outside Sec. Shield No BS-27A 341 No Yes No S.W. Quad.

MUF-40 Hx. Bldg. Outside Sec. Shield S.W. Quad 318 No No No Yes h Rx. g. u si e e. hield No No Yes MUE-kl 318 No S.W. Quad.

Rx. Bldg. Outside Sec. Shield BS-5 335 No Yes No No S.W. Quad.

BS-6 Rx. Bldg. Outside Sec. Shield Yes No No 335 No S.W. Quad.

Rx. Bldg. Outside Sec. Shield BS-26 337 No Yes No No S.W. Quad.

• • 8* " 81 ** hi No No No Yes DH-ll 297 S.W. Quad.

8* " 81 ** UI No No th Yes Dil-12 297 S.W. Quad.

Ex. Bldg. Outside Sec. Shield No Yes CF-7 297 No No S.V. Quad.

Ex. B3dg. Outside Sec. Shield No No Yes CF-8 297 No S.W. Quad.

Rx Bldg. Outside Sec. Shield No CF4 308 No Yes No S.W. Quad.

• 8* " 81 * 'I Yes No No BS-7 307 No S.W. Quad.

BS-22 S.W. s,pdg. No No No Yes uad. Outside Sec. SMeld 29' .

Hx. Bldg. Outside Sec. Shield No Yes BS-23 291 No No

_ S.W. Quad.

BS-24 w Hx. Bldg. Outside Sec. Shield 291 No 2 h Ye

& S.W. Quad.

"X* B d8' "8

• hi No Yes BS-25 293 No No S.W. Quad.

,m 4 .

TABLE 3.16.1 i '

SAFETY REIATED HYDRAULIC SNUBBERS Snubber In Snubber Snubbers Snubbers liigh Radiation Especially Inaccessible Accessible Snubber Area During Difficult During Normal During Formal ,

MK No. Incation Elevation Shutdown

• To Remove Operation Operation

x. Bldg. Outside Sec. Shield DH-23 295 No No No Yes S.W. Quad. '

Rx. Bldg. Outside Sec. Shield DH-214 ,

295 No No No Yes S.W. Quad.

Rx. Bldg. Outside Sec. Shield MS-208 338 No Yes No No N.W. Quad.

Ex. Bldg. Outside Sec. Shield MS-209 338 No Yes No No N.W. Quad.

Rx. Eldg. Outside Sec. Shield MS-210 338 No Yes No No N.W. Quad.

Rx. Bldg. Outside Sec. Shield MS-2H 338 No Yes No No N.W. Quad.

Rx. Bldg. Outside Sec. Shield MS-212 338 No Yer No No N.W. Quad.

Ex. Bldg. Outside Sec. Shield MS-213 338 No Yes No ho N.W. Quad.

MS-2g Rx. Bldg. Outside Sec. Shield 338 No Yes No No N.W. Quad.

Rx. Bldg. Outside Sec. Shield MS-215 338 No Yes No No N.W. Quad.

Rx. Bldg. Outside Sec. Shield MS-287 338 No Yes No No N.W. Quad.

Rx. Bldg. Outside Sec. Shield MS-288 338 No Yes No No N.W. Quad. _.

Rx. Bldg. Outside Sec. Shield FW G 2 320 No No No Yes N.W. Quad. _

x. dg. Outside Sec. SMeld FW 113 320 No No No Yes N.W. Quad.

Rx. Bldg. Outside Sec. Shield FW-108 320 No No No Yes N.W. Quad.

Ex. Bldg. Outside Sec. Shield '

FW-lll _ 320 No No No Yes N.W. Quad.

Rx. Bldg. Outside Sec. Shield DH-20 298 No No No Yes

, N.W. Quad.

DH-21 Rx. Bldg. Outside Sec. Shield 298 No No No Yes rJ N.W. Quad.

O'

• LT1

TABLE 3.16.1 BAFETY RELATED HYDRAULIC SIMBBERS Snubber Snubbers Snubbers Snubber In High Radiation Especially Inaccessible Accessible Difficult During Normal During Normal Snubber . Area During

• Elevation To Remove Operation Operation MK No. Location Shutdorne DH-22 Rx r? ?g. Outside Sec. Shield No No No Yes 295 N.W. Quad.

Int. Bldg. on MS-V-1D 355 No Yes No No MS-216 -

Int. Bldg. on MS-V-1C 3h1 No Yes No No NS-217 MS-218 Int. Bldg. on MS-V-lc 3hl No Yes No No h Int. Bldg. on MS-V-lc 355 No No No Yes MS-219 FG-220 Int. Bldg. on MS-V-1D 355 No No No Yes Int. Bldg. on MS-V-3D 341 No Yes No No MS-221 MS-222 Int. Bldg. on MS-V-1B 341 No Yes No No Int. Bldg. on MS-V-1A 341 No Yes No No MS-223 MS-22h Int. Bldg. on MS-V-1A 341 No No No Yes MS-225 Int. Bldg. on MS-V-1B 355 No No No Yes MS-226 Int. Bldg. on MS-V-lC 355 No No No Yes Int. Bldg. on MS-V-1A 355 No No No Yes MS-227 MS-289 Int. Bldg. on MS-V-1A 355 No No No Yes Int. Bldg. on MS-V-1B 341 No No No Yes MS-290 MS-228A--- Int. Bldg. on A RV Hdr. 337 No Yes No No Js MS-228BC7? Int. Bldg. on A RV Hdr. 337 No Yes No No st ~"'

MS-229 pg Int. Bldg. on B RV Udr. 337 No Ye' No No 2

Os

TABLE 3.16.1 1

SAFETY RELATED HYDRAULIC SNUBBERS '

Snubber In Snubbe.r Snubbers Snubbers High Radiation Eslecially Inaccessible Accessible Di ffichlt During Normal During Normal Snubber Area During MK No. Location Elevation Shutdown

• To Remove Operation Operation 16 -230 Int. Bldg. on C RV Hdr. 337 No Yes No No Int. Bldg. cn D RV Hdr. 337 No Yes No No 10 -231 -

MS-65 Int. Bldg. 314 No No No Yes MS-233 Int. Bldg. 314 No Yes No No g Int. Bldg. 314 No Yes No No MS-234 314 No Yes No No MS-235 Int. Blds.

Int. Bldg. 314 No Yes No No MS-236 Int. Bldg. 314 No Yes No No MS-237 MS-238 Int. Bldg. 314 No Yes No No Int. Bldg. 314 No Yes No No MS-239

.G-240 Int. Bldg. 314 No Yes No No MS-243 Int. Bldg. 314 No Yes No No Int. Bldg. 320 No Yes No No MS-277 MS-277A Int. Bldg. 320 No Yes No - No MS-247 Int. Bldg. Near EF-P-1 300 No No No Yes MS-245 Int. Bldg. Near EF-P-1 300 No No No Yes MS-246 Int. Bldg. Near EF-P-1 300 No No No Yes O Int. Bldg. Near EF-P-1 No No No Yes MS-270

' 300 N .

CB N

t TABLE 3.16.1 SAFETY RELATED IIYDRAULIC SFUBBERS l' Snubber In Snubber Snubbers Snubbers liigh Radiation Especially Inaccessible Accessible Snubber Area During Difficult During Kormal During Normal MK No. Location Elevation Shutdown

• To Remove Operation Operation MS-271 Int. Bldg. Near EF-P-1 300 No No No Yes W-121 '

Int. Bldg. B W Catch Ildr. 325 No No r yes W-122 Int. Bldg. B W Catch Ildr. 325 No No No Yes EF 'i4! Int. Bldg. Near EF-P-2A 302 No No No Yes EF-75 Int. Bldg. Near EF-P-2B 302 No Yes No No EF-76 Int. Bldg. Near EF-P-2B 302 No Yes No No EF-85 Int. Bldg. 302 No No No Yes EF-87 Int. Bldg. Near EF-P-1 302 No No No Yes EF-88 Int. Bldg. Near EF-p-1 302 No No No Yes EF-89 Int. Bldg. 305 No Yes No No W-ll6 Turb. Bldg. A W Catch Ildr. 323 No No No Yes W-ll8 Turb. Bldg. A W Catch Ildr. 323 No No No Yes DCll-58 Aux. Bldg. IIX Vault 286 No *Yes No No DCll-59 Aux Bldg. IIX Vault 286 No Yes No -

No DCII-68 Aux. Bldg. IIX Vault 286 No Yes No No NSE 2. Bldg. IIX Vault 286 No Yes No No 4.

NSB-13 & Aux. Bldg. IIX Vault 286 No Yes No No

4) _.

NSE-114 g Aux. Bldg. IlX Vault 286 No Yes No No

^7 CO

l TABLE 3.16.1 i

SAFM'Y RELATED liYDRAULIC SNUBBERS .'

Snubber Snubbers Snubbe:rs Snubber In High Radiation Especially Inaccessible Accessible Snubber Difficult During Normal During Normal Area During MK No. Location Elevation To Remove Operation Operation Shutdown

• NSE-15 Aux. Bldg. IIX Vault 28h No Yes No No NSE-16 - Aux. Bldg. IIX Vault 284 Ne Yes No No NSE-17 Aux. Bldg. HX Vault 284 No Yes No No MUE -6 Aux. Bldg. Valve Alley 283 Yes Yes yes No MUE-7 Aux. Bldg. Valve Alley 283 Yes Yes Yes No MUII-318 Aux. Bldg. Valve Alley 288 Yes Yes ye, No Mull-319 Aux. Bldg. Valve Alley 288 Yes Yes Yes No MUlf-321 Aux. Bldg. Valve Alley 288 Yes Yes ye3 No MUH-322 Aux. Bldg. Valve Alley 288 Yes Yes ye3 No Dilli-196 Aux. Bldg. 297 No Yes No No USE-7 Aux. Bldg. 295 No Yes No No NSE-8 Aux. Bldg. 295 No No No Yes NSE-9 Aux. Bldg. 293 No No No Yes NSE-10 Aux. Bldg. 291 No Yes No No NSE-ll Aux. Bldg. 291 No No No Yes NSE-18 Aux. Bldg. 291 No No No Yes NSE-33 $ Aux. Bldg. 297 No Yes No No

~3 NSE-37 '

Aux. Bldg. 293 No No No Yes y

n....- - . . . - . , . - ,

TABLE 3.16.1 SAFETY RELATED HYDRAULIC S!MBBERS Snubber In Snubber Snubbers Snubbers High Radiation Especially Inaccessible Accessible Snubber Area During Difficult During Normal During Normal

- MK No. Location Elevation Shutdown

• To Remove Operation Operation MUH-311 Aux. Bldg. N. End Valve Alley 295 No Yes No No MUH-312 - Aux. Bldg. N. End Valve Alley 295 No Yes No No DHH-187 Aux. Bldg. DH-P-1A Room 275 No Yes No No DHH-188 Aux. Bldg. DH-P-1A Room 275 No Yes No No SPSE-2 Aux. Bldg. DH-P-1A Room 275 No Yes No No SPSE-3 Aux. Bldg. DH-P-1A Room 275 No Yes No No SPSE-12 Aux. Bldg. DH-P-1A Room 275 No Yes No No DH.!-197 Aux. Bldg. DH-P-1B Room 275 No Yes No No DHH-198 Aux. Bldg. DH-P-1B Room 275 No Yes No No SPSE-7 Aux. Bldg. DH-P-1B Room 275 No Yes No No SPS E-10 Aux. Bldg. DH-P-1B Room 275 No Yes No No SPSE-11 Yes Aux. Bldg. DH-P-1B Room 275 No No No llh BS-19 Aux. Bldg. BS-P-1A Room 275 No *Yes No No SPSE-5 Aux. Bldg. BS-P-1A Room 275 No Yes No No SPSE-9 Aux. Bldg. BS-P-1B Room 275 No Yes No No BS-21 Aux. Bldg. BS-P-1B Room 275 No Yes No No Jr .

NSE-2 [ ] Aux. Bldg. 310 No Yes No No NSE-3 n ; Aux. Bldg. 310 No Yes No No

-1 CD

TABLE 3.16.1 SAFETY RELATED IIYDRAULIC SNUBBERS 8

Snubbers Snubbers  !

Snubber In Snubber High Radiation Especially Inaccessible Accessible Snubber Area During Difficult During Normal During Normal.

MK No. Location Elevation Shutdown

• To Remove Operation Operation i NSE-23 Aux. Bldg. NSP Discharge 322 No Yes No No NSE-24 - Aux. Bldg. NSP Suction 324 No Yes No No NSE-27 Aux. Bldg. 320 No Yes No No NSE-29 Aux. Bldg. NS to SF Cooler 320 No Yes No No g RW-72 Aux. Bldg. IIX Vault 290 No Yes No No RW-73 Aux. Bldg. HX Vault 290 No Yes No No RW-75 Aux. Bldg. HX Vault 290 No Yes No No RWE-8 Aux. Bldg. IlX Vault 290 No Yes No No RWE-9 Aux. Bldg. IIX Vault 290 No Yes No No RWE-10 Aux. Bldg. IIX Vault 290 No Yes No No RWE-11 Aux. Bldg. HX Vault 290 No Yes No No a

RWE-12 Aux. Bldg. liX Vault 290 No Yes No No RWE-13 Aux. Bldg. HX Vault 290 No Yes No No RWE-lh Aux. Bldg. HX Vault 290 No Yes No No IPE-1 Intake Pump House 290 No No No Yes IPE-2 "

Intake Pump IIouse 290 No No No Yes Yes IPE-3 $ Intake Pump House 290 No No No IPE-4 Intake Pump House 290 No No No Yes N

e

TABLE 3.16,1 SAFETY RELATED HYDRAULIC SNUBBERS Snubbers Snubbers I Snubber In Snubber liigh Radiation Especially Inaccessible Accessible Difficult During Normal During Normal Snubber .

Area During MK No. Location Elevation Shutdown

• To Remove Operation Operation Intake Pump House 290 No No No Yes IPE-5 IPE-6 -

Intake Pump House 290 No No Ho Yes -

a Intake Pump House 290 No No No Yes IPE-7 290 No No No Yes IPE-8 Intake Pump House Intake Pump House 290 No No No Yes IPE-9 CylinderJo y,,

Cylinder-Yes Resemdr-Yes RCP-1A Reactor Bldg. on RCP-1A 340 Reservoir-No seservoir-No Cylinder-No Cylinder-N y in r- a sen ir- es RCP-1B Reactor Bldg. on RCP-1B 34 0 Yes Cylinder-No Reservoir-No Reservoir-No Cy1 M er-N y e s sen es RCP-lc Reactor Bldg. on RCP-lC 340 Yes Reservoir-No Reservoir-No Cylinder-No Cylinder-N Cylinder-Yes Reservoir-Yes RCP-1D Reactor 31dg. on RCP-lD 340 Yes Cylinder-No Reservoir-No Reservoir-No Modificatior s to this table d te to changes in high radi ationnr-ne should ba nnhmi t + aa to the NRC t s part of the nex ; license amendment.

M N

W

,d N3 i

e

4.17 Shock Suueressors (Snubbers)

Aeolicability Applies to the inspection of hydraulic snubbers listed in Table 3.171 to deter =ine their operability.

Objective To provide assurance of the operability of the hydraulic snubbers.

Specification 4.17.1 All hydraulic snubbers whose seal =aterial has been demonstrated by operating experience, lab testing, or analysis to be compatible with the operating environment shall be visually inspected. This inspection shall include but not necessarily be limited to, inspection of hydraulic fluid reservoir, fluid connections, and linkage connections to the piping and anchor to verify snubber operability in eccordance with the following schedule:

Number of Snubbers Found Next Required Inoperable During Inspection Inspection or During Inspection Interval Interval 0 18 conths + 25%

1 12 months + 25%

2 6 months I 25%

3, h 12h days T 25%

5, 6. T 62 days _7 25%

>8, 31 days + 25%

The required inspection interval shall not be lengthen <ed = ore than one step at a time.

Snubbers may be categorized in two groups, " accessible" or

" inaccessible" based on their accessibility for inspection during reactor operation. Snubbers classified as " accessible" vill be inspected according to the above schedule. Scubbers classified as " inaccessible" vill be inspected according to the above schedule if plant conditions permit or during the first reactor shutdown thereafter.

These two groups may be inspected independently according to the above schedule.

h lT.2 All accessible hydraulic snubbers whose seal caterials are other than ethylene propylene or other caterial that has been demonstrated to be conpatible with the operating environment shall be visually inspected for operability at least every 31 days. Snubbers classified as inaccessible whose seal =aterials 1469 273

have not been demonstrated to be co=patible with the operating environ =ent shall be visually inspected fo'r operability at least every 31 days if plant conditions permit or during the first reactor shutdown thereafter.

4.17.3 The initial inspection shall be perfor=ed within 6 =onths from the date of issuance of these specifications. For the purpose of entering the schedule in Specification 4.171, it shall be assuned that the unit had been on a 6 =onth inspection interval.

k.17.h Once each refueling cycle, a representative sa ple of 10 snubbers or approximately 10% of the snubbers, whichever is .

less, shall be functionelly tested for operability including verification of proper piston =ove=ent, lockup and bleed. For each unit and subsequent unit found inoperable, an additional 10% or ten snubbers, whichever is less, shall be so tested.

Snubbers of greater than 50,000 lbs. need not be functionally tested.

Bases All safety related hydraulic snubbers are visually inspected for overall integrity and operability. The inspection vill include verification of proper orientation, adequate hydraulic fluid level, and proper attacbnent of snubber to piping and structures.

The inspection frequency is based upon =aintaining a constant level of

' snubber protection. Thus the required inspection interval varies inversely with the obsecved snubber failures. The nu=ber of inoperable snubbers found during a required inspection deter =ines the time interval for the next required inspection. Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the original required ti=e interval has elapsed (nc=inal ti=e less 25%) =sy not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval vill override the previous schedule.

Experience at operating facilities has shown that the required surveillance progra= should assure an acceptable level of snubber perfor=ance provided thet the seal =aterials are co=patible with the operating environ =ent.

Snubbers containing seal material which has not been de=enstrated by operating experience, lab tests, or analysis to be co=patibl, vith the operating environ =ent should be inspected more frequently (every month) until =aterial ec=patibility is confir=ed or an appropriate changeout is co=pleted.

Examination of defective snubbers at reactor facilities and caterial tests perfor=ed at several labcratories (Reference 1) has shown that

=illable gu= polyurethamdeteriorates rapidly under the temperature and =oisture conditions present in many snubber locations. Although

=olded polyurethane exhibits greater resistance to these conditions, it also =ay be unsuitable for application in the higher te=perature 1469 274

environ =ents. Data are not currently available to precisely define an upper te=perature limit for the =olded polyurethane.

Lab tests and in-plant experience indicate that seal materials are available, pri=arily ethylene propylene compounds, which should give satisfactory performance under the most severe conditions expected in reactor installation.

To further increase the assurance of snubber reliability,

! functional tests should be performed once each refueling cycle. These tests will include stroking of the snubbers to verify proper pisten movement, lock-up and bleed. Ten percent or ten snubbers, whichever is less, reprer.ents an adequate sample for such tests. Observed failures on these ,

sa=ples should require testing of additional units. Snubbers designated in Table 3 17 1 as being in high radiation areas j or those especially difficult to re=ove need not be selected for functional tests provided operability was previously verified.

Snubbers of rated capacity greater than 50,000 lbs. are exempt i

from the functional testing requirements because of the i=-

! practicality of testing such large units.

Reference (1) Report H. R. Erickson, Bergen Paterson to K. R. Goller NRC, October 7, 197h Subj ect: Hydraulic Shock Svay Arrestors i

I.

i 1469 275 I

i

i TABLE k.1-2

' MINIMUM EQUIPMEUT TEST FREQUENCY Item Times _ Frecuency

1. Coni-ol Rods . Rod drop times of all Each refueling shutdown full length rods

2. Control Rod Movement of each red Every two weeks, when reactor Movement is critical 3 Pressurizer Safety Setpoint 50% each refueling period Valves

h. Main Steam Safety Setpoint 25% each refueling period Valves 5 F.efueling System Functional Start of each refueling period Interlocks

6. Main Steam (See Section h.8)

Isolation Valves 7 Reactor Coolant Evaluate Daily, when reactor coclant System Leakage system te=perature is greater than 525 F

8. Charcoal and high DOP test on HEPA filters, Each refueling period cnd at efficiency filters freen test on charcoal any time work on filters for Control Room, filter units could alter their integrity and R3 Purge Filters

, 9 Spent Fuel Cooling Functional Each refueling period prior to -

System fuel handling I

l 10. Intake Pu=p House (a) Silt Accu =ulation- Each refueling period Floor Visual inspection of Intake (Elevation 262 Ft. Pump House Floor 6 in.) (b) Silt Accu =ulation Quarterly Measure =ent of Pu=p House i Flov l

l I

1469 276 b h-8

NRC PoHM 195 -

u.s. NUCLE AR REGUL ATOR Y F t .a SSION DOCKE T NUMBE R

42. re > g6_7gg NRC DISTRIBUTION Fon PAPT 50 DOCKET MATERIAL TO 2 ROM: DATE or ooCUMENT I Reid Metropolitan Edison Co 10-21-76 Reading, Pa R C Arnold oATE RECE:#Y-26-76 1

M LETTE R CNOTORIZED PROP INPUT FORM NUM8ER OF COPIES RECElvEO IC P; *. IN A L [UNC L ASSle lE D t' wP y 1 signed DESCRIPTION E NCLOSU RE Ltr trans the following: Amdt to OL/ Change to tech specs: Consisting of revisions with regard to typographical errors in previous submittals.........

Ojl.S f.ny. vm

,- V X

• PLANT NAME: Three Mile Island #1 TYCLNCE1.EDCeD z

SAFETY FOR ACTION /INFORMATION ENVTnn 11-5-76 ehf ASSIGNED AD: , _ , 'ASSICNr0 AD;

/ BRANCH CHIEF: l< t- t d (5) BRANCH PHTrF*

/ PROJECT MANAGER: Z vo # -htl4 PROJECT MANAGER?

Z LIC. ASST.: 1 M FrrvW7 LIC. ASST.!

INTERNAL DISTRIBUTION h REn3M SYSTEMS SAFETY PIANT 9YSTFvq SITE SAFETY &

/ NRC PDR HEINEMAN TFnegen ENVIRO AEAL'fSIS

/ I & E(2) SCHROEDER bENAROYA DENTON & MUT T eR 2_0El,D LAINAS

/ COSSICK & STAFF ENGINEERING IPPOLITO ENVIRO TECH _

MIPC MACCARRY KIRKWOOD FRNST CASE KNIGHT BALLARD HANAUER SIHWF7L OPERATING REACTORS SPANGLTR HARLFJS PAWL 1GKI STELLO 9TTP TFPH PROJECT MANAGEMENT REACTOR SAFETY OPERATING TECH. CASTT T.

~BOYD ROSS / EISENHUT STEPP P. COLLINS NOVAK / . SHA0 HUIuAN

_ HOUSTON ROSZTOCZY / BAER <

_ PETER _ SON CHECK / BUTLER SITFJiALYSIS I

_MELTZ / QRJMES VOLLMER HELTEMES AT & I BUNClf ,

SKOV110LT SALTZMAN / J J 0LLINS RUTBERG VPFCFU EXTERNAL UlSTHitlUTION CONTilOL NUMBE R f LPDR_:b ,s,3bo"a d_ l NAT_ LAB:

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