ML17208A421

Responds to NRC 800327 Ltr Re Lessons Learned Task Force short-term Requirements.Forwards Info Re Valve Position Indication,Instrumentation for Inadequate Core Cooling, Containment Isolation & Auxiliary Feedwater Flow Indication

ML17208A421
Person / Time
Site:	Saint Lucie
Issue date:	04/03/1980
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Reid R Office of Nuclear Reactor Regulation
References
RTR-NUREG-0578, RTR-NUREG-578 L-80-113, NUDOCS 8004080386
Download: ML17208A421 (31)

Text

REGULATORY i FORMATION DISTRIBUTION SY EM (RIDS) 1 ACCESSION NBR:8004080386 DOC ~ DATE! 80/04/03 NOTARIZED: NO DOCKET 0 FACIL:50 335 St. LUcje Planti Unit l~ Florida Power L Light Co, 05000335 AUTH a NAME AUTHOR AFFILIATION UHRIG~R,ED Florida Power 8 Light Co, RECIP ~ NAME 'ECIPIENT AFFILIATION REIDe R ~ W, Operating Reactors Branch 4

SUBJECT:

Responds to NRC 800317 it< re Lessons Learned Task Force short"term requirements,Forwards info re valve. position indicationiinstrumentation for ina'dequate core coolingi containment isolation 8 auxiliary feedwater flow indication ~

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FLORIDA POWER & LIGHT COMPANY April 3, 1980 L-80-113 Office of Nuclear Reactor Regulation Attention: Mr. R. W. Reid, Chief Operating Reactors Branch 84 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Reid:

Re: St. Lucie Unit 1 Docket No. 50-335 NUREG-0578 Short Term Re ui rements The attached information is being submitted in response to your letter of March 27, 1980.

Very truly yours, Robert E. Uhri g Vice President Advanced Systems 8 Technology REU/DKJ/cph Attachment cc: Mr. James P;- O'Reilly, Region II Harold F. Reis, Esquire 8c v>

S 8004 080384 PEOPLE... SERVING PEOPLE

ATTACHMENT 1 Re: St. Lucie Unit 1 Docket No. 50-335

'UREG-0578 Short Term Re uirements 2.1.3.a Valve Position Indication (1) ,

Provide your schedule for qualification of the valve position indication circuits.

~Res onse: Our vendor, Technology for Energy Corporation (TEC) has scheduled environmental testing and documentation to be complete by October, 1980.

2.1.3.b Instrumentation for Inade uate Core Coolin Provide a complete table of information regarding the subcooling meter as per Denton's October 30, 1979 letter.

~Res onse: This information is provided as Appendix A to this Attachment.

(2) Discuss the backup methods for monitoring subcooling margin.

Include in your discussion directions given to the operators by the procedures.

~Res onse: Manual use of steam tables provide the main backup to the subcooli ng margin monitor (SMM). To eliminate the need for hand calculations, a nomograph has been mounted prominently on the Main Control Board. The nomograph is a standard pressure versus temperature graph color-coded to show both the saturation curve and the 50'F margin-to-saturation curve. Procedures are bei ng modified to provide the operator with specific instructions to:

(1) With the SMM operating normally, use the nomograph in conjunction with the SMM to eliniinate dependence on a single instrument, or (2) With the SMM inoperable, use the nomograph utilizing control room indicators (TH, Pressurizer pressure, etc.) and core exit thermocouples to determine margin to saturation. Margin can also be determined by subtracting hot leg temperature from pr'essurizer temperature (Tsat as indicated by TE-1101).

Additional training will be given to both operators and shift technical advisors relative to these procedure changes and the use of the nomograph. All procedure changes and training will be completed prior to the unit's return to power following the current outage.

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Attachment A lists the minimum criteria for the subcooling meters. Provide your commitment to meet these criteria and your schedule for doing 'so.

~Res onse: St. Lucie Unit 1 will meet the criteria of your Attachment A by 1-1-81 or sooner sub'ject to equipment availability. The presently installed meter represents FPL's best effort to meet the NUREG-0578 criteria within NRC time frames and we believe our efforts met the intent of the short-term requirements. To do so, however, required utilizing installed instrumentation although the need to upgrade the installed instrumentation was recognized and efforts to define and implement the upgrade were initiated-Accomplishment of the upgrade requires and includes the installation of dual-element RTD's which will supply wide range hot leg temperature inputs to the Subcooled Margin Monitor (SMM).

Delivery of these RTD's is the limiting scheduling factor for the SMM upgrade (26 week lead time). We have requested our NSSS vendor (Combustion Engineering) to expedite delivery of the dual-element RTD's and C-E has indicated that they will do so and pursue the possible diversion of RTD's from other nuclear plants currently under construction.

(4) Provide the results of your evaluation of the need for additional instrumentation for detecting inadequate core cooling. Include a statement of your intent regarding design and installation of a reactor vessel level i nstrument.

~Res onse: The results of the subject evaluation were provided to the NRC in our response to I8E Bulletin 79-06C item 5. This submittal referenced C-E Report CEN-117, "Inadequate Core Cooling--A Response to NRC IE Bulletin 79-06C, item 5 for Combustion Engineering Nuclear Steam Supply Systems." This report concludes that sufficient instrumentation currently exists which is capable of detecting inadequate core cooling, and'PL concurs with that conclusion. Additionally, our plant engineering department has technically reviewed a number of current "state-of-the-art" designs for reactor vessel level indication and has concluded that none can clearly provide unambiguous indication of reactor vessel level.

Subsequently, while FPL will continue to assess the need for additional instrumentation, as well as review new developments in this area, we do not intend to install a reactor vessel level instrument at this time-2.1e4 Containment Isolation Provide a list of all essential and non-essential systems. Provide the basis for the classification of each essential system.

Specific references to CEN-125, where applicable, are acceptable.

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~Res onse: A list of essential and non-essential system containment penetrations is provided in Appendix B to this Attachment.

Essential penetrations (noted by an arrow in the margin) are defined as those containment penetrations for systems required to be oper'able to mitigate the consequences of an accident or to provide information to the operator necessary to follow the course of an accident.

(2) Verify that reopening of'closed, automatic isolation valves is accomplished on a valve-by-valve or penetration-by-penetration basis as opposed to group reopening.

~Res onse: Our review of the control systems of automatic isolation valves, as specified above, has concluded that reopening of these valves must be accomplished on a valve-by-valve basis. In particular,'he St.

Lucie Unit 1 design does not utilize "ganged" control switches for these valves, and thus each switch operates only one valve.

2.1.7.b Auxiliary Feedwater Flow Indication Document that you meet the redundancy part of this requi rement by use of steam generator level indication in addition to the auxiliary feedwater flow meters.

~Res onse: Under both normal operating and transient conditions, steam generator (SG) level provides the operator the primary input for regulating auxiliary feedwater to each generator rather than auxiliary feedwater flow. The St. Lucie Unit 1 control room is equipped with four independent safety-grade level meters for each steam generator. These meters are located within vi ew of the operator as he adjusts auxiliary feedwater flow to maintain SG level.

Regardless, additional positive instruction will be provided by procedure to the operator directing him to use SG level indication as well as flow indication to ensure that each steam generator is receiving auxiliary feedwater as appropriate. Procedure changes and training for operators and shift technical advisors will be completed prior to returning to power from the current outage.

2. 1.8. b Increased Ran e of Radiation Monitors Incorporate in your procedures the method for sampling for radioiodines and particulates in gaseous effluents from the plant vent and fuel handling building exhausts following an accident.

Provide the information requested in the October 30, 1979 Denton letter (pg. 35) for both release paths.

~Res onse: Plant procedures have been modified as specified above.

Specifically the procedures requi re measurement of background r adiation prior to sampling, the use of Silver-Zeolite filters for sample collection, and additional precautions and limitations to

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I minimize personnel exposure. Back-up power supplies are also specified. Additional information requested by the October 30, 1979 Denton letter was provided to the NRC audit team March 24-25, 1980.

(2) Implement plant modifications and procedures for monitoring',

atmosphere steam dump valves and steam safety relief valves following an accident. Provide the information requested in the October 30, 1979 Denton letter (pgs. 33-34).

~Res onse: Existing procedures have been modified to address plant modifications for monitoring the atmospheric steam dump valves and the steam generator relief valves. Continuous monitoring under accident conditions is accomplished by routing main steam to a

,single channel analyzer via a one inch blowdown line upstream of the main steam isolation valves and a sample cooler. Information requested in the Ocotber 30, 1979 Denton letter was provided to the NRC audit team March 24-25, 1980.

2.1.8.c Im roved In-Plant Iodine. Instrumentation Revise your procedures to assure that the control room and TSC will be monitored for radioiodine following an accident with the portable cart mounted samplers.

~Res onse: An existi ng plant procedure will be modified by April 30, 1980 to require the transfer of an NMC portable monitor to the Technical Support Center (TSC) if and when the TSC is activated. As the TSC and control room are adjacent, this instrument can be used to monitor both areas.

2.2.1.a 'hift Su ervisor SS Res onsibilities Provide a commitment to annually reissue the management directive that emphasizes the responsibility of the SS for the safe operation of the plant.

~Res onse: Since the TMI accident, management directives as specified above have been issued. FPL will continue to issue these directives at intervals of one year or less.

(2) Describe typical accident situations when you believe the SS should be permitted to leave the control roan. Modify your procedures to direct that the SS not leave the control room unless, in his opinion, it is necessary for plant safety.

~Res onse: There are a number of, accident conditions under which it may be necessary for the Nuclear Plant Supervisor (NPS) to leave the Control Room in order to make a personal evaluation of a given situation. An actual example of this occurred some time ago involving a hydrogen fire in the main generator. After verifying that the primary plant (NSSS) was shutdown and stable, the NPS left

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the control room for the scene of the fire to ascertain the status of firefighting efforts and to determine the potential for and consequences of spreading of the fire. Similar scenarios can be visualized for hurricanes, flooding, and other like situations. r FPL does recognize, however, that there are other accident situations during which the NPS would be required to remain in the Control Room. To stress this point, plant procedures will be revised to emphasize the necessity for the NPS 'to remain in the Control Room under accident conditions unless, in his opinion, his personal evaluation of the situation is necessary to maintain plant safety. One additional point should be noted. Current NRC regulations require the scheduling of only one SRO per Control Room operating shift. It is and has been FPL practice to schedule two SRO's (Watch Engineer and NPS) per operati ng shift in the Control Room ~

(3), Provide a commitment for an annual review of the SS's administrative duties. This review shall be performed by the senior person responsible for plant operations.

Res onse: Existing plant procedures will be modified to require an annual review of NPS administrative duties as specified above.

(4) Provide assurance that the SS will spend a minimum amount of time on routine administrative duties (Items 1-4 and 8, 3-13-80 memo).

~Res onse: Routine administrative duties of the NPS will be defined such that a maximum of 30 minutes per shift is allocated to duties specified as items 1-4 and 8 (3-13-80 memo).

2.2.1.c Shift and Relief Turnover Procedures Provide a description of the method you have established to evaluate the effectiveness of the shift and relief turnover procedures.

~Res onse: The St. Lucie Unit 1 gC Department has scheduled surveillance of Operations Department compliance to procedures. Shift relief and turnover will be surveilled on a periodic basis as part of this program to determine their effectiveness.

2.2.2.a Control Room Access Clarify procedure to indicate that line of succession for the Nuclear Plant Supervisor is limited only to personnel holding a Senior Reactor Operator's License.

~Res onse: The Control Room Access procedure will be revised as necessary to specify that the NPS can be relieved by qualified personnel holding a valid Senior Reactor Operator's License.

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2.2.2. b Technical Su ort Center TSC Describe dedicated communications between the TSC and the control room, and the TSC and the Emergency Operations Facility.

~Res onse: Sound powered phones will be instal led to provide dedicated communications between the TSC and the Control Room. A dedicated commercial telephone link will be established between the TSC and the Emergency Operations Facility.

(2) Describe the manner in which the plant operating parameters will be transmitted to the TSC. Justify that the best effort was made'to have a data display in the TSC.

~Res onse: Efforts to establish a data display in the TSC have been and conti nue to be intensive. Initial short-term efforts revealed no simple method of transmitting control room data to the TSC without possibly compromising Control Room information. For example, the existing plant "computer" (DDPS) is of such limited capacity that it cannot be used to transmit data to the TSC. Additional efforts considered new systems ranging from television cameras to expensive and exotic computer systems. These efforts included site visits by vendors, presentations by vendors, and trips to vendor's facilities to observe systems in action. Due mainly to technical inadequacy and/or equipment lead times outside the NRC time frames, these systems were rejected in so far as short-term objectives were concerned.

Additionally, discussions with the NRC indicated that the need, in the short-term, for a TSC data display diminished with the distance between the TSC and the Control Room. (The TSC at St. Lucie is immediately adjacent to the Control Room and contains a viewing window). Consequently, it appeared reasonable, again for the short term, to perform this function, if required, by dispatching an individual from the TSC to the Control Room to transmit the data required.

Efforts were then concentrated on meeting the long-term (1-1-81) upgrade requirements. For reasons which include those discussed earlier, FPL decided to combine the function of the TSC data display with the computer planned for purchase to meet the NRC Appendix I requirements. Parameters to be included were selected (See Appendix C) and engineering begun to incorporate the added parameters into the overall design. Purchase of equi pment, however, was held in abeyance pending formal NRC definition of Appendix I requi rements, including Technical Specifications.

Subsequent discussions with the audit team on March 24-25, 1980 which resulted in this particular position of your March 27, 1980 request, have indicated a possible NRC concern that FPL has not conducted a "best effort" in this area. We state unequivocably that this is not'o- As an indication of our recognition of NRC concerns relative to data display in the TSC, FPL has proceeded 6

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,with the purchase of the Appendix I computer. This system is currently scheduled to be installed and operational by October 1980.

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AppENDIX A INFORMATION RE UIRED ON THE SUBCOOLING METER

~Dis la Tmar = Tsat 'Trc or Pmar = Prc Psat Information Displayed (T-Tsat, Tsat, Press, etc.)

Disp1ay Type (Analog, Digital, CRT) Di ital Continuous

'ontinuous or on Demand Sin le Single or Redundant Display RTGB-103-Reactor Location of Display Coolant System Portion T-Tsat Alarms (include setpoints) T-Tsat = 30oF Normal Operation:

Overall Uncertainty ( F, PSI)

+5F, +35psi High I'inergy Pipe Break

+ 250 psi See attached curves Range of Display Tmar O to 2OO F Qualifications (seismic, environmental, IEEE323) IEEE Std 344-1975 IEEE Std 323-1974 less a in )

Calculator Type (process computer, dhdicated digital or Dedicated Micro-analog calc.) com uter If process computer is used specify availabi-lity. (% of time) N/A Single or redundant calculators Sin le Selection Logic (highest T., lowest press) Highest T measured lowest P measured for'sat Qualifications (seismic, environmental, IEEE323) IEEE Stds 323 & 344 less a in Calculational Technique (Steam Tables, Functional Fit, ranges) Steam Tables and Interpolation routines

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~Zn ue Tempera ture (RTD ' or T/C ' ) RTD's Temperature (number of sensors and locations) 6 sensors 4 Cold Leg 2 hot le )

Range of temperature sensors 465 615 F Cold Leg 515 665 F Hot Le Uncertainty of temperature sensors ( F at 1) +2 F Qualifications (seismic, environmental, IEEE323) See 79-01B res onse Pressure (specify instrument used) Pressure transmitters Pressure (number of sensors and locations) 2 (split range),

Pressurizer Range of Pressure sensors 0-1600 psia

'1500-2500 sia Uncertainty of pressure sensors (PSI at 1) 27.4 psi Qualifications (seismic, environmental, IEEE323) See 79-01B res onse Backu Ca abilit Availability of Temp & Press TIA-lllQ Hot L'eg TIA 1121j PI-1102'IC 1104 J Pressurizer Availability of Steam Tables etc. Nomo ra h'n RTGB Training of operators Operators have been initia11 -'trained

• Procedures Procedures are being revised

~Additional training, as described in our response to 2.1.3.b(2) will be conducted A-2

@5 psN F.ter Empac.t on Temp, Hargfo (oF) 5 P'rror L ct en Pressure Hwgfn (PSIA 420 - - 52'b Coolant Tea@ f TYPlCAL SuaneiED NNlil NArTOR LHSTNHBfr SYSTEM UHCERQfHGRS DURING BNN EHFf%Y PERE BREAKS A-3

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CCO'TA1%BRT PBZTFKTIOP ACD ISOLATIOS VALVF. ISFOLVATIOB tionn Locatfon Rorno?

Reforence Second- Valve co Prfasry CIS ary Y s xi null Posftfon Pcno- I'ere- Isola Flov Conte?a- Ywthod Actua- .z hod Closure Vith Foct-trstfon trscfon tfon Dfrec- nent Valve Type asd Pipe of of T~ Valve Pover Accfdcnt Rusher Se'roice T?pe Clsss tfon Vessel Tss Rukcr Sire Closure Chasse? Closure ~sec Position Failure Positfon 1d2 Yxfn Stesa Yfafn Sccsa C Out Outside Stop (MlCV<8-?A,S) 34N BSIS Air Accuau Closed Closed lscor Feedvstcr Feedvster C In OutsMe Cate (I-Y:49-7,8) 20N SIAS or HSIS Bsnfvhee? 60 As Is Closed!

Irc Ovtsdg Ga?c (i-wMI.'ll +N dfAS cr k@5 Heck(s4d 4o A,S (h CIOSzA Outside Chcc'k (I Nl9 2SS) Autoastfc Bsndvheel Auxf1fsry Fccdvctcr Auxflfsry Feedvetcr Zn Outside Chec'k (I-V~<50) 4N Autoastfe In OutsMe Check (I-V49-350) 4N Autonstfc In Outsfde Check (Z-V 09+350) 4N Au oastfc In Outside Chec'k (I-V49-350) 4N Au toast c f 546 Stean Ccsorstor Slovdovn Slov4ovn I? I C Ouc Outsfde Clobc (I-FCV-23-3, 5) 2N CIS 10 Closed Closed Prfnsry Bskeup Voter Bskcvp Voter ZI Al Zn Outside Check (I V 15 1347) 2N Autosst is Ineuc Check (I-V-15-1347) Autcascic

('m (.Zccf-ZB-C ) CCC. (8)

Locked Closed Q?5M Closed Scscfon Afr Supply Statfon Afr A2 In 0 teide Clo'be (I-V-18-947) 2N Bsnucl ~

Oucsfde Clobc (I-'V-18-947) anus? Locked Closed Closed OucsMe Check (I-V-18 957) ZN Antosstfc Cate (I-N-18-?)

1 lnstrunent Afr Supp?y ?nsttuuent Afr Al In OutsMe CIS A Bendvhee? 30 Clos e4 closed Close4 Inside Check (I-V-18-957) ~ Au toast? c ficctfng Vent- Al Outside Sucterfly (I-FCV-IH) CIS A Hend&co? Clos cd Closed Closed 10 Ccncsfneont Putfo Afr 4 OuC Closed ilating OutsMc Sucterfly (I-FCV-2$-5) . 48N CIS A Handvbcel Closed Closod gxhsust Inside Sot tartly (I FCV-25-4) CIS 8 B acdvn eel Clos c4 Closed Closed (I FCV-2$ -1) Closed Cloced Closed t

Contcirecnt Furge Beating d Vent- Al In Outside gut ter fly CIS Bsndvhcel

• flst'ng Outside gutter? ly (I-FCV-25-2) 48" CIS Bsndch col Closed Closed Closed Supply Closed Closed.

Inside gut terfly (?-FCV 2S-3) CIS Bsadvhee? Closed I, 13 Spore Al Zn Outside Clobe (V-6741) ZN CIS S Open Close4 Closed 14 Vitro?en Supply to Reste Ynnegenent ZZ Autonstfc Safety la)ection Tanks Outsfde Check (V&779) lf, 17 Contsfnsent Fsn Coolers Cosponent IZ C Out Ovtsfde gutter? ly Rcaotc- Hsndvheel Opca Open (I-SS-14-5) Typ Bsnusl 19 ~ 21 Cooling Heter Return Cooling 16, ZS Ccntsfnnent Fan Coo ers Cosposent IZ C In OucsMc Sutterfly SN Rcaote- Baedvhce} Opnc Open

(?-SS 14-5)Typ O'Ius?

20, 22 Coolfrg Heter Cooling Supply'eactor Coupoaent ZI Al In Outside Sutterfly (I BC'r 14-7) 8" SIAS 8 Bcndrhee? S Open Closed Closed Coo?ent Pusp Closed Close4 Coo fng Hs er Supply Cooling Outside Sutterfly (14CV-?4-?) SIAS A Bsndvheel 5 Open ZI Al Out Outsfde Sut ter fly (IdlCV-14<) 8" SIAS Hsr dvhoc 1 5 Open Clos cd 'losed 24 Reactor Coolant Fvep Couponenc Closed Closed Cooling Heter Return Cooling Outside 'Suttctfly (I-LCV 14 2) SIAS HscONhee? 5 Open (e) ) P(FQtltklcd ~ C~ll~

Locct fon Rc fcrerne Secon4- Valve o Prfnsry CIS cry Ysaaiuuu Po sic Post ion'ich Pene- Pono- Isola Plov Contain- %thod Actus~ Yathoa Closure

'losed tration trot ion cion Df rec ncnc Valve Type and Pipe of cion of Ttao Eo mal Valve Povcr AccHcnr Raraha r Sa'rvtco Typo Class t ton Vessel a Stre Ctosurb Cr canal Closure ~scc Pos t c foaa Fsiluro Post'ctoaa 45 Fuel Trenaf<<r Tube Fqet Pindling V ln/Out InsMe Double Cos'becca Flange N" Closed 26 Lccdovn Line Chenicsl 4 111 2II Out Instde Clobe (V-2515) 2" CIS ~ SIAS S Open Closed Cloaca Volu~ Control Inside Clobe (V 2516) Cts, SIAS A Open Closed Closed OuCsidc Clobe CIS A Opoa CloscC Closed Casrgtng tne Caacnfcat 6 111 E In Outs Me Check (V-2403) 2N Autoaatfc Volune Control 26 Reactor Coolant Sscpz ing 111 7 I Ouc Outside Clobc (V 5200) 3/6" CIS 5 Closed Cloaca Closed

'O Closed Scnple tisae Ciobc (V-520)) 3/6" CIS 5 Closed Cloaca 29 Pressuitcer Sacro Linn Ssnple Scapi ing zz'z. Out OutsiCe OatsMe Clo'be (V-5201)

Clobe (7-$ 204)

CIS CIS A

3 CloseC Clos cC Closed Cloaca Closed Closed Prcssurtrcr Stem Space Smpling III 'Sl Oucsidc Clobe (V 5202)

Clo'be (V-$ 20$ )

)Ig" CIS CIS Closed Closed Closed Closed Closc4 Clos e4 Smple OutsMe 30643 Stean Cenerctor )lovaovn Ssepling 111 C Ouc Outsice Clo'be (I PCV 23-7) I/2" Cis 10 Open Cloaca Closed Scaple Outsfde Clo'be (I-PCV-2)-9) Cfs 10 Open Cloccd Closed 31 Concainnent Vane tfesder Vesta I'1 Alc Out Outsf4c Cate (V-6554) 1 la Czs 5, Open Cloaca closes Closr4 Closed Ynnsgcacnt Outefde Cate (V-6555) CIS 5 ~ Open 32 4 3) Contcirncnc Sunp suction Eccrgmcy IV E Out Outside Sutter fly (I-tt747-2Aah) 24" Renote Ynnusl Closod As Is Open on RAS Core Cooling 34 6 3$ Concsinnenc Spray Concnfr~nc Il E Outsfde Clo'be (I-FCV47-IAa)) 12" Reacts ffanus1 Closed Open on CNC,'pen Host Rccovsl OutsMe Cate (I-V47-1514) Yznucl Locked Opm Inc ido Check (I-V-07-155)) 10" Autonstic

)6 4 )9. Ssfecy In)eccfon Eaergcncy III E In OutsMe. Clubs (ECV 361)a16al7 ~ 6 Reacts-Ysnusl Closed As Zs Open on SIAS Core Ccoltrg 2$ ,26,27 ~ )5,35,37,45,$ 6a47)

Outside Check (V-3114,1)a24a23>34a Auconatic 33,44,43)

ShutCovn Cooling Encrgency 111 Sz OuC Inside Cate (V 3651,V-3461) lou Renst e-Ymus I Locked Closed As Is C'ose4 Core Cooling Inside Cate (V )652,V )460) Reacts-Yncusl locked Closed As Ie Closed Safety In)cotton Tank Eucrgcncy Core Coolfng lll S2 Out OutsMc Outside cate (v-3463)

Cate (I-V<3 1307) 2" Yenucl Yanucz Loc'kcd Closed Locked Closed Closed Closc4 Test Line AI Out OucsMe Clobe (I-LCV<7 '11A) 3 ~

CIS, SIAS 10 Closed Closed Closed Resccor Csvtcy Sunp Waste Cloaca Closed Closed Pan.'p Discharge nn s gcccn t Outside Clole (I-LC7-07-113) CIS, SIAS 10 IV Ale Out Ou cide Clobe (V-6301) Cls 10 Open Cloaca Closed Resccor Drain Tank Vssce 10 Open Closed Closed Panp Suctfon Nsnsgcncnt OutsiCe Cate (V-6302) CIS Reactor Coolant Pucp Controlled Sleedof f Chcnicsl 6 Volvne Control III, 31 Outside InsMc Cate (V 2$ 0$ )

Solano ia (Z-SE-Ol-l) 3/4" CIS CIS Open Open Closed Closed Closed Closc4 Sot ~ penccrstioa as defined by AS% s 6 PV Code, Section III, Class NC, Iten h~ 1132, Footnoce 2 (Sascaer 1$ 72 Addenda).

82 Out Glcaloa (Ic)f-C8 lE) >IS CAN /b. <lesrA sr BZ. Out Qolcfe 5 Rv- bb.tF) Va) cl5 8 +cas& Closed CleSak

Locscfon Re(create Second Vslve to Priasry CIS 4ry f xun Posit fon

?cas- isola Flou Cont4fn- Y4thod Actus Yfcthod Closure Vith Post-

?cas- of tfoa of Tfnc Eorncl reive ?ever Accfdent tration tration tven DirCC ncnt Valve Type snd Pipe Position Fsilure Position Class tion Vessel 5 Sire Closure Qmrwl Closure -~SCC

~ Sucker 45 d 53 Service Fluid Instruncnt Scnsirg Lire for Vsculss Rcl fcf EestlnS d Vcntilctfon TIEc D ln/Gut Outside Excess Flou Check 3/8" Autons ic 1 PofucllnS Cevfty Purl flee ion 'Flov Inlet tuel Pool Cicsnup AZ ln ' tsido inside Cato (I-V-07-1609)

Cata (I-V-07-1609)

Cate (I-V-07-1609)

Msnwl Nsnusl

)fsnwl Loclcd Closed Locked Closed Locked Closed Closed Closed Closed 47 Rofuolfnf Cavity tuel Pool A2 Out Outside Purificsrfon Flov Outlet Cleanup Inside Cate (Z l'-07 1609) nus1 Locked Closed Clos od Coutsfcwnt A2sc Out Iasfde Solenoid (I-FSE-27-1, 3/8" Emote-Nsnwl Closed Closed Closed/Open Epdrof ca Scnplfna Lines - Saxplo Hydrofcn 2,3,4)

Sa~ I inS Outside Solenoid (I FSE 27-8) Resets-Msnusl Closed Closed Closed/Open Nydrofcn Sscplind Contefoacnt A2" 4 ln Inside Check (I-V-27-1341) 3/8" Autonst ic Lines - Scapi'eturn MydroEcn Outside Solenoid (I FSE 27-10) 3/8" Rcuo tc-Y~w1 Closed Closed Closed/Open SczplfnE acier to I'cnctrstion Eo. 33 Spsre 51 Bydrodcn Ss-plina Contefrncnt AIsc Out Iasfds Solenoid (Z-FSE-27-5 ~ 3/8" React&howl Closed Closed Closed/Open Lines Sapie Myd rodeo 6,7)

ScaplfnS Outsid>> Solenoid (I-FSE-27-9) 3/8" Rcnotc-Y4nwl Closed Closed Closed/Open Lydroica Secplfna Contsfoccnt A2CC In Inside Check (I V-27 1342) 3/8 II Autonstic Lines Ssuple return OutciC4 Soleno 1 d (I-FSE-27-11) 3/8" Rcnstc Anwl Closed Closed Closed/0?cn H~HCS Contefnwnt Atnosphcre Rsd Istion ZI Al Out Inside Clobo (I-FCV-26-1) CIS A Rendu%eel 10 Scc O?cn Closed Closed Radiation Msnftorina Monf torlnS Outfsde Clobc (I FCV 26 2) a Esnduhecl 10 Scc Open Closed Closed Systcn 528 Contafnncnt Atnospbcro Radiation Al Out inside Clobe (I-VCV-26-3) 1" CIS A Bsnduhcel 10 Sec Closed Closed Rsdfstion ".unitorfnS Yfonftorfaa Outside Globe (I-FCV-26-4) a Esnbkccl 10 Sec Closed Closed

~ uc Syston Contsfnucnt Atnospherc Rsdfetlon Monftorfna Systcn Radiation Yionitorfna Al ln nsfde Outside Clobe (I-FCV-26-5)

Globe (I FCV 26 6)

CI8 A 8

Rsnb,+eel E~vheol 10 Scc 10 Scc Oven O?ca Closed Closed Closed Closed 520 ILRT Controlled Lcsksde Intefrcted Lech . Inside Clobe (I-V<0-1325) lu Locked Closed Closed Closed Manual Loc'kcd Closed Line R4tc Test Outside Clcbc (I V-00-1325) IN Closed Closed Msnwl 52E ILRT Pressure Scnsina Intcarcted Leek A2 Out Ins,fde Globe (I-V<0-1322) Locked Closed Closed Closed 3/8" Mcnuel Loc'kcd Closed Closed Closed Lfno Rate Test Ostside Clobe (I-V-00-1322) 3/8" Msoucl 53 Refer to Pcnotrstfon Eo. 4$

>v Location Reference Second Volvo to . Prinsry CI5 cry Y~fcun losltfoa Peoe- Pent- Isola- Floe Contafn- Y~thod Actus tbod Closure Bith pcs t Ifno trstion BI>>her Service ~I trstion TLTe cion Dfrcc-Class tion nent Vessel .'I Valve Typo and Pipe Slee of Closure tion Channel of Closure ~Sec Rornel Valve Pssf t'lo'>

Pcve Failure r Accfdcac Peeftfon 54 ILRT Pressurfting and Integrated Les'k II AI ln/Out Insfde Ffengc Su Closed Closed Closed Dcpressurfsfrc Line Rate Tact Outside Caco (I V OOSOI j ~ 1 6" teeusf Locked Clo>ed Closed Closed 55 Spare 56 Bydrogen Purge Outside Cental~at Il A2 In Outsfdc Cate (I V-25-11) tf>nusf locked Closed Closed Air YMeup Bydrogcn Purr o Outside Cate (I-V-2$ Yanusl locked Closed Closed (BSV)

-12)'1 57 4 56 Bydrogen Purge R>d>Suet Cootafr~n Al Out -

Ou sfdo Cate (I-V-25-15>15) Ynnual ioc cd Closed Closed Bydrogen Purge Outcidc Cate (I-V 2514,16) Nsnusl Locked Closed Closed (Bdv) 59 4 60 Do Rot Penetrate Contaf>u>ent Vcsscl 61 To 65 Do Bot Penetrate Ccntaf~nt Vessel 64 Refer to Penetration Xo. 40 65 4 66 Do Bot Penetrate Contafncant Vessel

6) 6 62 Contsfnnent Vscuun Relief II Al ln Irside Cbec'k (I-V-2520,21) 2'> Autosstfc Outside Dutterfly (I.FCV 25- 24'> Closed Closed Closed 746)

Although this fs, a class Al penetration, the piping ls seisalc Class I on both sfdes of contsinncnt.

Although this is a class A2 penetration, tho piping forns c closed sclsnlc Class I systen outcldc contcinnent.

APPENDIX C Sample Type Parameter Quanit Class IE Where Available Rate Si nal Comments

~RC S stem Hot leg temperature No On DDPS 10 sec- Analog 3. per:RCS-Hot Leg Cold leg temperature No On DDPS 10 seu Analog -1 per RCS Cold Leg Pressurizer Level (WR) No Instr Cab 10 sec Analog Pressurizer Pressure No Instr Cab 10 sec Analog PORU & Safety Ualve No Instr Cab 1 min Contact Alarm Indication Steam S stem Steam Generator Pressure On DDPS 10 sec Analog Steam Generator Level Instr Cab 10 sec Analog Aux FW Flow Yes Instr Cab 10 sec Analog ECCS H. Head Safety Injection Flow Yes Instr Cab 10 sec Analog Containment Containment Pressure Yes Instr Cab 1 min Analog Cohtainment Sump Level. New 1 min Analog Air Ejector Radiation App. I Comp. 1 min Analog Containment Radiation App. I Comp. 1 min Analog

t Sample Type Parameter. uanit Class IE Where Available Rate Si na1 Comments Noble Gas Activity App. I Comp. 1 min Analog Vent Stack Particulate Activity App. I Comp. 1 min Analog Vent Stack Radioiodine App. I Comp. 1 min Analog Vent Stack Meteorolo ical Wind Speed No App. I. Comp. 1 min Analog Wind Direction No App. I. Comp. 1 min Analog