ML19225C447

Submits Response to NRC 790308 Request for Addl Info Re CR3 Pump & Valve Inservice Insp Program.Revision to CR3 Procedures Will Be Completed within 90 Days from Date of NRC Approval

ML19225C447
Person / Time
Site:	Crystal River
Issue date:	07/25/1979
From:	Stewart W FLORIDA POWER CORP.
To:	Reid R Office of Nuclear Reactor Regulation
References
3--3-A-3, 3-0-3-A-3, NUDOCS 7907300343
Download: ML19225C447 (131)

Text

Florida Power

' f) 54 P / 3HA1l July 25, 1979 File:

3-0-3-a-3 Mr. Robert W.

Reid Chief Operating Reactors Branch #4 Division of Operating Reactors U.S.

Nuclear Regulatory Commission Washington, D. C. 20555

Subject:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Dei.r Mr. Reid:

Enclosed for your review is Florida Power Corporation's response to your letter dated March 8,1979, requesting additional information concerning the CR#3 pump and valve inservice inspection program.

The three sets of the drawings referenced in our submittal will be submitted on or before July 31, 1979.

Upon notification from your office that the ISI program for CRl/3 has been approved, Florida Power Corporation will make the necessary re-visions to the CR#3 Surveillance Procedures to incorporate the approved program.

The revision to the CR#3 procedures will be com-pletud within 90 days from the date of NRC approval.

If you require any further discussion concerning our submittal, please contact this office.

Very truly yours, FLORIDA POWER CORPORATION 1

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Stewart 7

Manager 4 (g h Nuclear Operations 790730034]{

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General Office 3201 nmtsourtn s reet soun. P O Box 140c St Pete st;u g Fuli 3f 33 e 813 626 5152 r

STATE OF FLORIDA COUNTY OF PINELLAS W.

P.

Stewart states that he is the Manager, Nuclear Operations, of Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief.

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Stewart Subscribed and sworn to be f o re me, a Notary Public in and for the State and County above named, this 25th day of July, 1979 f

Notary Public Notary Public, State cf Florida at Large, fly Commission Expires: August 24, 1983 (CrockettNotary 2 D12) 434 2M

FPC RESPONSE TO SRC REQUEST FOR ADDITIONAL INFORMATION DATED MARCH 8, 1979 The attached responses address all questions contained in Enclosures 1 through 4 of your March 8, 1979 letter.

Each res ponse references an applicable drawing or section of the CR 43 In % cvice Inspect ion Program where the in fo rmat ion request ed is located.

As stated in our cover letter, the drawings referenced in our response are being marked to identify our response information and will be furnished on or before July 31, 1979.

A complete copy of the CR #3 Inservice Inspection Program, which has been extensively revised to reflect the NRC's positions, and the result s of necting held at CR 13 with NRC representat ives is included in this submittal.

Simpson(NRCResp)D4 h

ENCLOSl:RE 1

!!echanical Engineering Branch

Response

1.

See Table B,

babers 4 and 5, Page 2.

Res po ns e 2.

See Table B, Numbe r 1, Page 1.

Response 3.

See Table B,

?: umbers 7, 8, 10 and 11, Pages 2, 3, and 4.

Res ponse 4.

(a) No relief request ed, except Table B, Number 2, Page 2.

(b) No relief requested, except Table B, Number 2, Page 2.

(c) No relief requested, except Table B, Numbe r 2, Page 2.

(d) No relief requested, except Table B, Number 2, Page 2.

(3) No relief requested, except Table B, Number 2, Page 2.

Simpson(NRCRerp)D4

'34 PJ A

ENCLOSURE 2 Reactor Systems Branch Response 1.

DHV-1, 2:

See Decay Heat System, FD-302-641, Table 2A, Numbe r 1, Page 1 of 3.

CFV-2, 4:

See Core Flood Systec, FD-302-702, Table 2A, Number 1, Page 1 of 2.

CFV-1, 3:

See Core Flood System, FD-302-702, Table 2A, Numbe r 2, Page 1 of 2.

Response 2.

DHV-5, 6:

These valves are not being operated in the normally open position at power and power is not removed.

Res ponse 3.

Maximum st roke t imes for all valves are based upon safety funct ion ope rat ion.

Res ponse 4.

DRV-11, 12:

None, see Decay Heat System, FD-302-641, Table 1, Page 1 of 1.

Response 5.

DHV-33, 3 6:

It is not necessary to leakchcck these valves as the emergency procedure, EP-106, ' Loss of RC/RC Pressure", requires that the ES signal :o DHV-34 and 35 be bypassed (BWST isolation valves) and shut when shif tind to RB sump from the B'r ST.

Additionally, there is an elevation dif ference that would act allow RB sump flow to the BWST Response 6.

DHV-7, 8:

No ne, see Decay Heat System, FD-302-641, Table 1, Page 2 of 2.

Respotse 7.

DRV-39, 40: See Decay Heat System, FD-302-641, Table 1, Page 2 of 2.

Response 8.

CFV-27:

Correct, see Core Flood System, FD-302-702, Table 1, Page 1 of 2.

Response 9.

RPI Check Valves :

See Bbkeup & Purification System, FD-302-661, Table 2A, Number 1, Page 1 of 9.

Re s po nse 10.

DHV-110, 111:

See Decay Heat System, FD-302-641, Table 2A, Number 2, Page of 3.

Response 11 MUV-23, 25, 26:

See ikeu p & Purificat ion System, FD-302-661, Table 2A, Number 1,

Fasis for Relief, Page 1 of 9 for MUt

'2, 36, 37, 160, 163 and 164.

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ENCLOSURE 2 (Cont'd)

Response 12.

(1) See Reactor Coolant System, FD-302-651, Table 1, Page 1 of 1,

• Remarks".

(2) See Attachment A.

Response 13.

See revised Valve Test Program Tables 1, 2 and 2A.

Response 14.

DRV-33, 36:

Sec Decay Heat Syst em, FD -30 2-6 41, Table 1, Page 2 of 2, "Rema rks".

MUV-42, 43, 36, 37, 160, 163, 164:

See Makeup &

Purification System, FD-302-661, Table 2A, Numbe rs 1 & 2, Pages 2 & 3, " Alt e rnat e Testing".

MUV-10, 11, 1, 7, 2, 6 :

See Makeup & Purification System, FD-302-661, Table 2 A, Numbe r 3, Page 3,

" Alt ernat e Test ing.

CFV-2, 4 1, 3:

ee Core Flooding System, FD-30_-702, Table 2A, Numbe rs 1 & 2, Pages 1&, " Alt ernat e Testing".

Response 15.

RCV-4, 5, 6, 7, 103:

These are operating convenience valves.

Dropped froc program.

DHV-91, 93:

See Decay Heat System, FD-302-641, Table 2A, Numbers 3&4, Page 2.

RCV-53, 12, 13. 14:

See Reactor Coolant System, FD-302-631, Table 2A, Numbers 1, 2, 3 & 4, Pages 1&2 Res po nse 16.

$JV-9, 3, 3, 4:

Diese valves will be open during normal plant operation per ECCS S=all Break Analysis Solution for Crystal River Unit 3 (see May 29, 1979 NRC Safety Evaluat ion ).

Th e re f ore,

valves will be dropped froa prograc as operating convenience valves.

MUV-69, 68, 62, 63:

These are operating convenience valves and are dropped from the program.

MUV-59, 66, 70: These are uaintenance valves for operating convenience only, not included la our program.

434 9+,

Simpson(NRCResp)D4 4j,

ENCLOSURE 3 Cont ai nment Syst e=s Branch Response 1.

See revised Valve Test Program Tables 1, 2 and '

It has been verified that all valves that receive either a c ont ainment isolation signal or a safety injection actuation signal are included in the program.

These valves are so denoted in the "Re= arks" column of Tables I and 2.

Response 2.

See Att achment A, Crystal River Unit 3, Inservice Ins pect ion Program, Number III, " Cat egory

'A' Valves - Leak Rate Testing".

Response 3.

!$V-130, 148:

Se. Main and Reheat Systea, FD-302

'.1, Table 2A, Numbe r 1, Page 1 of 1.

FWV-29, 30:

See Feedwate r Syst en, CD-302-081, rable 2A, Numbe r 1, Page 1 o f 5.

DWV-162:

See Condensate & Demineralized Water Supply, FD-302-182, Table 2A, Numbe r 1, Page 1 of 1.

DWV-160:

See Condensate & Denineralized Water Supply Syst em, FD-302-182, Table 1 SWV-79, 80, 81, 82, 83, 84, 85, 86:

See Nucl 2r Services Closed Cycle Cooling Syst em, FD-30.-601, Table 2A, Nuuber 1, Page 1.

SWV-109, 110:

See Nuclear Services Closed Cycle Cooling System, FD-302-601, Table 2A, Number 2, Page 1.

SWV-35, 37, 39, 4',

43, 45:

Blese valves do not perform a saf ety funct ion, receive no RS isolation signal, and do not have to change position.

Their normal and safety position is open.

Therefore, their only function is for carntenance purposes.

These valves are recoved f rom tL e program.

DHV-1, 2, 3, 4:

See Decay Heat System, FD-302-641, Table 2A, Numbe rs 1 & 5, Pages 1 & 2.

DHV-5, 6:

See Decay Heat Systen, FD-302-641, Table 1, Page 1.

MUV-18, 27, 49, 253, 259, 260, 261:

See Makeup &

Pur ificat ion Syst em, Table 2A, Numbe rs 4, 5, 6 &

7, Pages 3,4,&5.

Simpson(VRCResp)D4 fY' ' 47O,,&

ENCLOSURE 4 Auxiliary oyst ras Branch Response 1. 0 "SV-Il5, 135, 116, 133:

These valves are dropped from progrus as operating convenience valves.

Response 2.1 ASV-50:

Valve will be tested at re fue ling s.

See Auxiliary Steam, FD-302-051, Table 2A, Number 1, Page 1.

Response 3.1 EFV-2, 1, 7, 8, 15, 16, 17, 18:

2ee Energency Feedwa:er System, FD-302-082, Table 2A, Numbers 1, 2 L 3, Pages 1 & 2.

EFV-11, 14, 32, 33_:

See Emerdency Feedwater Systea, FD-302-082, Table 1, Page 1, "Recarks".

Response 3. 2 EFV-2:

Valve is normally closed.

It is electrically interlocked to prevent opening with a condenser vacuum.

Res pons e 4.1 FWV-161, 162:

Due to TMI-2 incident, valves will be in the throttled open position.

See Feedwater lystem, FD-302-081, Table 1, Page 1.

Response 4.2 EJV-34, 35, 43, 33, 157, 158:

See Feedwater Systen, F D-302-081, Table 2A, Numbers 4, 5& 6, Pages 2 &

3.

Response 4.3 FWV-45, 46:

See above Table 2A, Numbe r 7, Pages 3 & 4.

Response 5.1 DFV-47, 48:

Valves shall be quart erly st roked.

See Energency Diesel Generator Fuel Oil Transfer System, FD-302-281, Table 1, Page 1, "Renarks".

Res ponse 6.1 EGV-25, 26:

Valves shall be quarterly stroked.

See Energency Diesel Generator Comp. St art ing Air,

FD-301-282, Table 1, Page 1, "Recarks".

Response 7.1 SWV-59, 60, 63, 64:

Tnese valves are for maintenance when isolating the chilled water system from the Nuclear Se rvices System.

Th e re f o re, these valves are not included in the program.

Response 7. 2 SWV-103, 104:

These valves are normally closed, and therefore are not included in the program.

Operat ing convenience valves.

Simpson(NRCResp)D4 f (/ j R

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ENCLOSURE 4 (Cont'd)

Response 7.3 SWV-579, 60 7:

Diese valves are for maintenance when working on the emergency feedwater pumps 3A and 33 and therefore not included in the program.

Response 7.4 SWV-584:

Maintenance valve, not to be included in the program.

Response 8.

SFV-7, 34, 5j):

%> c S pe n Fuel Cooling FD-302-621, Table 2A, Numbers 1, 2 & 3, Pages 1 & 2.

SFV-54, 85, 87, 89:

See Table 1 of above section.

Diese valves shall be quarterly st roked.

Responce 9.

DCV-186, 188:

These are maintenance valves for isolating nitroden from the Decay Heat Closed Cycle Surge Tank, the refo re not included in ths prograa.

Response 10.1 MUV-16, 31:

See Makeup & Parificat ion System, FD-302-661, Table 2A, Number 8, P3de 5.

Res ponse 10.2 MJV-27, 36, 37, 163, 164, 53, 257, 30, 17:

See Makeup &

R2rif icat ion Systea, FD-302-661, Table 2A, Numbe rs 5, 1,

8, & 9, Pages 1, 5 & 6.

MUV-4, 8, 63, 68:

See Attachment A or question response to, Quest ion 16.

MUV-107:

This is an operat ing convenience valve, therefore not included in the program.

Response 11.1 CAV-58, 61:

See Chemical Additional System, FD-302-671, Table 1, Page 1, and Table 2A, Nu ab e r 1, Page 1.

Response 12.1 WDV-321:

There has been a modificat ion to this port ion of the Liquid Wast e Sysr ea and a downst rean check has been added to the system.

The class break is now at the downstreaa check (FD-302-681, Co-ord.

r-15) which makes this valve non-safety related.

Th e re f o re, valve is dropped froa prodran.

Response 13.1 DOV-209:

Elis valve shall be stroked at ciurterly int e rvals per Sect ion XI requ'_rement s.

Response 14.1 RWV-32, 33:

These are operating coreenience and maintenance valves and are therefor. removed from the program.

Res ponse 14.2 RWV-40, 41, 17, 18, 21, 22, 24:

These are maint enance valves for component isolation and therafare removed froa the program.

Simpson(NRCResp)D4 h

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37 g RIVER ISSEgv1C7 73s?ECTIO3 ??s0C; W 434 23r

CONTENTS ATTACH'ENT A.

. Crystal River Unit 3 Inservice Inspection Pisgram ATTACH 1ENT B

. ASSE Section XI Pump & Valve Test Program for Crystal River Unit 3 ATTACH'ENT C.

. Valve Code Table ATTACH'ENT D.

. List of Valve Table Symbols ATTACH 3ENT E.

. Valve Test Program >! atrix for Tables 1, 2, & 2A ATTACH 3 INT F.

. Abb reviations Tab le A.

Pump Test Program TABLE B Pump Tes t Program Requests for Relief TABLE 1 (by system)

Valves being tested in accordance with Code Requirenents TABLE 2 (by system)

Valves for which relief is reques ted.

TABLE 2A ( by system)

Valve Relief Request Basis, f

23$

ATTACli"ENT A Page 1 of 2 CRYSTAL RIVER UNIT 3 INSERVICE INSPECTION PROGPX!

I.

Identificaticn of Class 30undariet - Class 1, 2, and 3 boundaries were established as identified in Figure 1 of this submittal in accordance with the Code of Federal Regulations (10CFR 50.50.2(v),

Re gulatory Guide 1.26, Rev.

3, and ANSI N18. 2a-19 75.

II.

Cold Shutdcwn - Inservice Inspection a)

For inservice inspection requirecents for testing those valves which require stroking or seat movement during cold shutdown, the testing of the subject valves will commence for those periods of cald shutdown, as defined in the CR#3 Technical Specifications, which are expected to exceed 48 h u.s.

This is the milimum tire we feel is required to make the necessary arrangeneaus to schedule personnel to accorplish this cold shut dow: testing. As many valves as possible will be tested during this cold shutdown.

However, ccid shutdown will not be extended solely because of cold shutdown valve testins.

b) Should a valve fail to exhibit the required change cf valve stem position and cc ctive action is initiatea during cold shutdown, an assessm'nt of system operability shall be made in relatienship to tne component's inoperability.

The acticn statetent of the facilities technic.d specifications shall then be followed.

Therafore, relief is requested from the

" Corrective Actica" subparagraph of P73-3A10 (g) conce rning cold shutdown valves and unit startup.

III.

Cate go ry 'A' Valves - Leak Rate Testing - Catetory

'A' class 1, 2, and 3 valves are subdivided into types in the CR-3 Pump and Valve Test Program.

These types are those being leak tasted in accordance with 10CFR50, Appendix J, type C as specified in the f acilities technical specificatione as containment isolacien valves and those valves which perform a pressure isolation functica from a high pressure system to a icw pressure system.

These valves are noted in the Valves Test Program as SLT-1 and SLT-2, respectively.

For these valves denoted as SLT-1 1; is requested the Appendix J, type C, test be substituted for the Secticn XI leak testing as provided by IWV-3420 of the code.

The cctbined leakage of al:

these valvea and other penetrations subj act to a type

'3' and 'C' Appendix J test shall be less than 0.6La. percent /24 hours),

where La is the maximum allowable leakage. t Pa, the calculated peak containment internal pressure as speciflad ir the facilities technical specification.

2%

Page 2 of 2 Relief is requested frca subparagraph I'iV-3420 g) (1).

The alternate prcposed cethod of specifying a maxi.um permissible leakage on each SLT-1 valve shall be an admini strative high leakage limit o r "a ction" limit.

This limit shall be based upon 95% of 0.6La, where La is in standard cubic feet per minute of leakage, and "norral inches of valve diameter", excluding the type "B"

penetrations and the 48" reactor building purge valves. Where valves exceed their individual actica limit, they should be replaced or repaired and retested as judiciously as possible.

For valves denoted as SLT-1 and 6 inches and larger, s ubparagraph IWV-3420 (g)(2) shall be followed.

Type SLT 2 valves shall be individuall'/ identified by system and alternate test plans discussed in the " Request for Relie f" table.

IV.

Sys tems Other Than Those Containing S team, Wate r, and Radioactive Waste - For systets containing fluid other than steam, water, and radioactive waste which are cla=s '

2, and 3 shall not be tested in any other manner relative to Seccien XI requirements than those specified in this submittal for pump and valve inservice testing.

V.

Technical Specifications - Should a conflict arise between the In-service.aspection Program and the Technical Specifications, Florida Power Cotperation w!11 propose to the NRC a Technical Specificaticn Change Reques t, should the testing requirements of Seccion XI be core restrictive.

VI.

Authori: ed Inspector - (AI) - Florida Power Corporation requests exemption froc the requirements o f IWA-1300(f) and IWA-2120 (a through h),Section XI, 1974 Edition, thrcugh Su==er 19 75 Addenda.

"'he Crystal River Nuclear Plant is under no boiler code legislatien and has no local, cunicipal, regional or State enforcetent author-ity.

We feel that Florida Power Corporation's Quality Assurance Program and the Regulatory Auth irity, the Nuclear Regulatory Coc-mission, provides.are than sufficient insurance that the examina-tions, pressure tests, and pump and valve testing required by Section II, ASSE B & PV Code are enacted and enforced.

g Revisien 1 7/23/79 h

ATTACHMENT o Revisica 1 7/79 Page 1 of 3 ASME SECTION XI PDT AND VALVE TEST PROGRAM FOR CRYSTAL RIVER UN.i 3 1.

Pump Testing Program A.

The purp test program was developed employing the classifi-cation guidelines contained in 10 CFR 50.2(v) for Quality Group A, Regulatory Guide 1.26, Revision 3, and ANSI-N18.2a-1975 for Quality Groups B and C.

(Quality Group A is the same as Class 1, Group B is 2, and Group C is 3.

Using these guidelines and I'JP-1100, the pu=p list attaened as Table A was developed. Table A identifies the following:

1.

The purp number and service it p e r f o rts, along with the P & ID on which it is f o un d.

2.

The following test quantities:

Speed Inlet Pressure Differential Pressure Flow Rate Vibration A=plitude Bearing Terperature B.

The period for which the pump test program is applicable is the 20-tonth period cotrencing March 13, 1977.

C.

The pump test progran shall be conducted in accordance with Subsection IWP of Section XI of the 1974 Edition of the ASME Boiler and Pressure Vessel Code through Summer 1975 Addenda, except for specific relief requested in accordance with 10 CFR 50.55a(g)(5)(iii) which is identified in Table P of th. Pump Tes ting Program.

D.

Table B identifies those test quantities required by the appli-cable code for which a request for relief is written.

Table B identifies the following:

. System

. Test Quantity Basis For Relief Alternate Testing p'

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Page 2 of 3 II.

Valve Testing Program A.

The valve test program was developed employing the classifica-tion guidelir.es contained in 10 CFR 50.2 (v) f or Quality Group A,

Regulatory Guide 1.26, Revision 3 and ANSI 18.2a-1975 for Quality Groups ' md C, (Quality Group A is the same as ASME Class 1, Group B is 2, Group C is 3.

B.

The period for which the valve test program is applicable is the 20-menth period co cencing March 13, 1977.

t.

The valve t es t progran shall be conducted in accordance with Subsection IWV of Section XI of the 1974 Edition of the ASME Boiler and Pressure Vessel Code through Summer 1975 Addenda, except f or specific relief requested in accordance with 10 CFR 50.55(g)(3)(iii), which is identified in Tables 2A.

D.

Figure 1 identifies the drawings which were used to develop the valve test program, together with the number of pages contained in Tables 1, 2, and 2 A.

E.

Tab le s, 1, " Valves Being Tes ted In Accordance With Code Eequire-cents", are divided by system and identi21es the follcwing for Category A, B, C, D and E valves:

Valve Number Code Class P & ID Coordinates Valve Category (all Category A valves will be leak tested at the same (or greater) frequency as scheduled refueling outages, but not less than once eve ry two years. )

Sice, type and actuator (see Attachment D).

Test During 1 = Quarterly frequency testing 2 = Cold Shutdown frequency tes ting 3 - Pe fueling f requency tes ting Test to be performed (see ' Valve Code' Tab le, Attachrent C Leak rate valve ( Cate go ry

'A' valves only).

F.

Tables 2 " Valves for Which Relief Is Requested", are divided by systen and identifies the folicwin g for category A, 3, C, D,

&E valves:

Valve Number f

Pege 3 of 3 Code Class P S ID Coordinates Valve Category Size, type, and actuator Test during 1 = Quarterly frequency of testing 2 = Cold Shutdcwn frequency cf testine 3 = Re fueling f requency of tes *.ing Test to be perforced (see Valve Code Table, Attachment C)

Leak rate valve (Cate gory ' A' val /es only)

Basis for relief, Table 2 A, reference nucher G.

Table 2A " Valve Relief Request Basis" provides further ampli-fication and justificatica for the spc. fic relief requested.

Included in this Table are the follcwing:

Syste Valves Function Test Require: ent (witich relief is requested)

Basis for Relief Alternate Tes ting g

24f

ATTACa'E::T C Page 1 of 3 VALVE CODE TABLE CODE FOR VALVE TEST l'ETHODS & 3MXI3'Di FL1L STRCKE TI:ES CATEGORY A-B VALVES EF-lF Exercise valve (full stroke) every 3 cenths to Section 3:1, IWV-3410(a).

EF-lP Exercise valve (part stroke) every 3 centbs to Section XI, IWV-3410(b).

EF-2F Exercise valve (full stroke) at cold shutdown as allcwed by Section XI, INV-3410(b).

EF-2P Exercise valve (part stroke) at cold shutdcun.

EF-3F Exercise valve (full stroke) at refueling.

EF-3P Exercise valve (part stroke) at refueling.

EF-5 Exercise valve (with f ail-safe actuators) ta observe failure code eve ry 3 tenths to Section XI, IWV-3410(e).

EF-6 Exercise valve (with f ail-safe actuators) to observe failure mode at cold shutdown, to Section XI, IWV-3410(e).

ET-1 Exe rcise valve - p owe r operated (full s troke) and reasure time (2 sec. rax.)Section XI, IWV-3410(c).

ET-2 Exercise valve - power operated (full stroke) and reasure time (5 sec. max.) Sectica XI, IWV-3410 (c).

ET-3 Exercise valve - pcwer cperated (full stroke) and ceasure time (15 se c. max. )Section XI, IWV-3410 ( c).

ET-4 Exercise valve - power operated (full stroke) an d =c as ure tire (25 sec. tax.)Section XI, IWV-3410 ( c).

ET-5 Exercise valve - power operated (full strcke) and ceasure time (40 sec. max.)Section XI, IWV-3410(c).

ET-6 Exercise valve - pcwer cperated (full stroke) and reasure ti=e (46 sec. ma:r. ) Sectica XI, IWV-3410 ( c).

$ 2'/g

Page 2 of 3 ET-7 Exercise valve - pcwer operated (full stroke) and reasure time (60 sec. ma:<. )Section XI, I'cV-3410 (c).

ET-3 Exercise valve - pcwer operated (full stroke) and reasure tire (120 sec. max.) Section X1, IWV-3410(c).

SLT-1 Cate;ory "A" valve, seat leak test valve during refueling, but less than every two (2) years by 19 CFR 50, Appendix J, type C.

SLT-2 Category "A" valve that pe rf o rms a pressure isolecian function.

PV-1 Operational checks with appropriate recov-entries shall record the positica of these passive valves befe.- operaticas are per-forced and af ter cperations are cc=ple.ed.

(1) Passive valves are valves that are not required to change position to accceplish a safety-related function.

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CATEGORY C VALVES Page 3 of 3 EF-lF Exercise valve ( full st roke) every 3 months,Section XI, IWV-3520(a).

EF-lP Exercise valve (part stroke) eve ry 3 nonths, Secticn XI, IWV-3520(b).

EF-2F "xercise valve (full stroke) at cold shutdevn,Section XI, IWV-3520(b).

EF-2P Exercise valve (part stroke) during cold shutdown.

EF-3F Exercise valve (full stroke) at refueling.

EF-3P Exercise valve (part stroke) at refueling.

TF-3 Safety and relief valve test (set point) t;Section XI, Table IWV-3510-1.

SLT-1 Cate gory "A" va lve, seat leak test valve at re fueling, but less than every 2 years.

SLT-2 Category "A" valve, perf or s a pressure isc '. ation function.

CATEGORY E VALVES OC-1 Cperational check of valves (veritication if either locked cren or locked closed before and af ter cperation) to Section XI, Article IWV-3700.

h 247

ATTACH"ENT D Page 1 of 1 LIST OF VALVE TABLE SY BCLS

! SY330L NOMENCLATUFI i

i VALVE TYPES I'

3F BLTTERFLY CK CHECK DA DI APH RAGM GA GATE GL GLOBE ND NEEDLE FIG REGl'LATO R REL RELIEF / SAFETY 3 -w'Av SCK STOP CHE.

.__.._--.---..CE ACTL'ATOR TY_ PES _ _.

i A

AIR M

MA';UAL M0 MOTOR SA SELF ACTUAIED SO SOLENGID VALVE POSITION C

CLOSED LC LOCKED CLOSED 0

0PE:i LO LOCFID OPEN i

T'd THROTTLED

-4 24f

ATTACH:ENT E Page 1 of 2 VALVE TEST PROGRAM 19.TRIX FOR TABLES 1, 2, and 2A ISD DIAGPZLS NUMBER OF PAGES SYSTEMS NU'!BERS T-1 T-2 T-2A MAI:I AND REHEAT SYSTEM FD-302-011 2

1 1

AUXILIARY STEAM E -302-051 1

2 1

FEEDWATER FD-302-OS1 2

2 5

ESERGENCY FEEDWATER FD-302-082 2

1 2

CONDENSATE FD-302 '01 1

CONDENSAIE AND DEMINERALIZED ' WATER SUPPLY FD-302-182 1

1 1

CHEMICAL CLEA'i1NG STEA'1 GENERATORS FD-302-192 1

D03ESTIC WATER FD-302-211 1

INSTRU"ENT AIR AND STATION AIR FD-302-271 1

E>'ERGENCY DIESEL GENERATOR FUEL OIL TRANS FER FD-302-281 1

1 1

EMERGENCY DIESEL GENERATOR COMPRESSED STARTING AIR AND ENGINE E:GIAUST FD-302-282 1

1 1

JACKET COOLANT SCHEMATIC DIAGPAM FD-302-283 1

1 1

AIR COOLER COOLANT SCHEMATIC DIAGPXI FD-302-284 1

1 NUCLEAR SERVICES CLOSED LYCLE COOLING FD-302-601 2

2 2

$Tsk n,

Page 2_of 2 T-1 T-2 T-2A NUCLEAR SERVICES A'iD DECAY HEAT SEA '4ATER FD-302-611 1

SPENT FUEL COOLING FD-302-621 1

1 1

DECAY HEAT CLOSED CYCLE COOLING FD-302-631 1

1 1

DECAY HEAT FIMOVAL FD-302 -6 41 2

2 3

REACTOR COGLANT FD-302-651 1

1 2

RAKEUP AND PURIFICATION FD-302-661 2

4 9

CHEMICAL ADDITICN FD-302-671 1

1 1

LIQUID SAMPLING FD-302-6 72 1

NITROGEN AND HYDROGEN FD-30 2-6 7 3 1

LIQUID '4ASTE Dl POS AL FD-302-6 81 1

GAS '4ASTE DISPOS AL FD-302-691 1

CONTAINMENT MONITORING FD-302-693 1

COPI FLOODING FD-302-702 2

1 2

FIACTOR BUILDING 5 PRAY FD-302-711 1

1 2

FIACTOR SUILDING PRESSURE SENSING AID TESTING FD-302-712 1

REACTOR SUILDING LEAR RATE TESTING AND POST ACCIDENT HYDROGEN PURGE FD-302-722 1

PIACTOR BUILDING FUEL HANDLING A"dA AND AUXILIARY BUILDING FD-302-751 1

INDUSTRIAL COOLER '4ATER FD-302-762 1

CHILLED '4ATER FD-302-756 1

434 286

ATTACRhZNT F E* 1 1

ABB REVI ATIONS The following standard abbreviatiens are used by Florida Pcwer Corporation and may be found through this document.

EWST Borated Water Storage Tank CF Core Flood CR-3 Crystal River Unit #3 CRDM Control Rcd Drive Mechanisa DH Decay Heat E FTB-1 Stean-driven Energency Feedwater Pump Turbine ESA Engineering Safeguard Actuation FPC Florida Power Corporation HPI High Pressure Injection LPI Lcw Pressure Inj ectio-ML-Main Steau 3'SRM

>Lin Ste Rupture Matrix MU Make-up Purification OTSG On'e through steam generator RB Reactor Building RC Raactor Ccolant d

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l'a r,e I of 2 TAlli.E A - PUttP TEST l ItnCRAFI Prepa reil by 7/16/79 Date Test Quantities l' ump Coor-Inlet DI. f fe rent i al Flow Vib rat ion Bearing Test Piunp tlunibe r !1 nates Speed Pressure Pressure Rate Amplitude Temperature Iu erval n(l)

PI AP Q

V

'lh (2) iloitl e A C l 3

AP-1 A E-5 No YES (3)

YI:S YES NO (4)

FIO (5)

UEEKIY (FD-302 -671)

CAP-1B E-5 NO Yl:S ( 1)

YES YES NO (4)

NO (5)

W EE El.Y l

lill l i.111 NG llSP-I A E-6 NO YES YES Yl:S YES YES QUARTERI.Y w

SPRAY u

(FD-302 -711 )

IIS P-I 11 l'- 6 No YES YES YES YES

'YES QUARTERI.Y 4

I)l{ CAY llEAT lu:P-1 A C-2 11 0 YES YES YES YES YES yllAR I ERI.Y Cl.0S EI) CYCL.E N

COOI. I flG Q (FD-302 611 )

liC P-1 in D-2 No Y i.:S YES YES YES Y ES QUARTERI.Y r

I)ECAY lil:AT DllP-1 A G-10 FIO YES YES YES YES YES QUARTERI.Y Imfl0 val.

(FD-302 - 641 )

1)llP-l li G-12 NO YES YES YES YES YES QU Altl ERI.Y lil: CAY llEAT RUP-l A F-3 No Y l'S (6)

YES tlO (7)

YES YES QUART Eltl.Y S MitV lC E Sl{AWATl R (FD 'lO2-31 I)

RWP-3B F-5 NO YES (6)

YES NO (7)

YES YE5 QUARTERI.Y 171ERGENCY EFP-1 F-5 11 0 YES YES NO (H)

YES YES QUARTERI.Y FEEDWATER (FD-302-OH2)

EFP-2 C-5 YES YES YF"

!Jo (8)

YES

'YES QUA RTEltl.Y EMERGENCY RWP-2A F-4 NO YES (9)

YES t!O (10 YES YES QUAR'l ERI.Y NUCl. Fall NE RV '..E SEAU T!:R (FD '?)2 611 )

Rul'- 215 F-5 NO YES YES (9)

NO (10 )

YES YES QUARTERI.Y NUCI. EAR SWP-1A F-13 NO VT.

YES YES YES YES QliARTERI.Y Sl:ltVICl{S Cl USl'.I) CYCI.E SU P-i ll C-13 fl0 YES YES YES YES YE!

411 ARTERI.Y COMIING

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Page 1 of 4 TABLE B PUMP TEST F70GPX1 REOUESTS FOR RELIEF 1)

SYSTEM:

All Class 1, 2, and 3 pump: as listed in Table A unless specifically noted.

TEST OUANTITY:

n, Speed BASIS FOR PELIEF:All motor drivers are synchronous or induction type except the steam driven emergency feed water pump, EFP-2.

The rotative speeds are not required to be measured en these pumps (except EFF-2 as notel) by subarticle IWP-4400.

Speed shall be measured at each test on EFP-2 only.

2) SYSTEM:

All Claas 1 2, and 3 pumps listed in Table A, unless otherwise specifically noted in Table 3 herein.

TEST REOUIREMENT Subarticle IW-3400, frequency of inservice tcsts, subparagraph IWP-34DO (a) requires an inservice test performeu nomina 111 each month during normal plant operation.

BASIS for RELIEl It is unnecessarv to measure and record all pump test parameters each month to determine if pump shall fulfill its function.

Using probabilistic analysis as for the basis for relief, with reference to the followin2 papers,(1) "Possible Criteria Which Can Supplement the Single failure Criterion" (Draft Capv) Arril 12, 1976, and (2) "A Note on Beliability and Safety Evaluatians: Cptimal Test Intervals Considering Test Downtimes", both by W.

E. Vesely, U.

S.

Nuclear Regulators Conmission, Probabilistic Anal zsis 3raneh.

We request an extended period of three (3) months between inservice pump tests.

ALTERNATr TESTING: An inservice test in accordance eith subarticle IUP-3100 <ill be performed quarterly unless otherwise specifically noted.

The pump shall be exercised monthly to allow an oil film on bearing, prevention of shaft sag, bearing brinelling, liquid stagnation, lubrication stagnation, and prevention of seals or packing fren corroding or stagnating at the rubbing interfaces.

3)

S Y S TE.'h Chemical Addition COM Pm;r?_:T S :

CAP-la and CAP-13 TEST CUANTITY Pi, inlet pressure BASIS for RELIEF: There is not a pressure tap available for meunting a gage t o no t.

suction pressure.

In order to install a pressure tar, a system modification would ce required to a Class 3 system The modificatien would require a pressure test on the Class 3 system.

This would involve draining and flushing the boric ac 3 system.

ALTW,' TE ~'ESTING: Suc t ica p res sur e shall be calculated M the level in the coric acid storage tanks.

434 25j/

Page 2 of 4 TABLE B PUMP TEST PROGRMt RECCESTS FOR RELIEF

4) SYSTE:f:

Chemical Addition COMPONLNTS:

CAP-la and CAP-1B TEST OUANTITY:

V, vibration amplitude CASIS FCP P"T.IEF-This is a hermetically sealed pump.

' lib r a t ion readings on the se type pumps do not forewarn of pump failure because of the outside mass being so tarce.

Total failure would occur before sicnificant dynamic imbalante would be noted on vioration readings.

Additionally, the pumps are totally encased with insulation to prevent boric acid from crystallicing at low temperatures.

ALTERNAic. i t.m I::C : These pumps shall be tested weekly in recirculation.ade and flow measured.

A minimum flow shall be achieved at each weekly test to determine operability.

This flow shall be commensurate with its safety operation.

Preventive mainter.ance snail be performed at intervals recommended by the manufacturer.

3) SYSTEM:

Chemical Addition COMPONENTS:

CAP-1A and CAP-13 TEST CUANTITY:

Tb, Ecaring Temperature BASIS for RELIEF: This is a aermetically sealed pump.

The pumping medium furnishes lubrication for the internal bearings.

Total failurs would occur before significant temperature increases would occur at the pump casinz.

ALTERNATE TESTING:

weekly operability checas shall be performed on ti e sa pumps.

6)

SYSTE:D Decay Heat Service Seawater COMPONENTS:

R'.iP-3 A a nd R'.iP-3 3 TEST CUANTITY:

Pi, Inlet Pressure EASIS for RELIEr-There is not a pressure tap installed in the suction line c: these pumps o measure inlet pressure. The installaticn of a tap would require a odification to the system involving a violation of the pipe pressure boundary.

The modification aould entall tests in accordance with the Constructica Code and Section :I, Class 3 Svstem.

ALIFDNAT" TEST-Inlet pressure shall be calculated by the tide level.

7)

SYSTFM:

Decay Heat S e r'f i c e Seawater CCMPONr'TS:

?J.i?- 3 A s R'.JP-3 3 TEST O'sNTITY:

Q, Flow Rate BASIS for RELIEF- ~here is not a flow element installed in the disch ar;e line af taeso ocaps to

asure tre ficm rate.

The installation of in element 434 25 Cf

Page 3 of 4 TABLE 3 PUMP TEST PROGPE REQUESTS FOR ?ELIEF 7) aASIS for RELIEF: would require a rodification of the pipe p ressure bounda ry.

CONTINUED This modification would entail exacinations and tests in accordance with the Ccastruction Ccde & Secticn XI for the Class 3 System.

ALTERNATF TESTI:;G: This system is of fixed resistance.

Flow reasured is not necessary when the resistance may be fixed.

8)

SYSTEM:

Emergency Feedwater CC"PONF';TS :

EFP-1 and EFF-2 TEST GUA'TITY:

Q, Flcw Rat e BASIS f or RELIEF-There is not a ficw element installed in the discharge line of these pumps t o re as u re the ficw rate.

The inst allation of an clerent would require a modificaticn of the pipe pres-sure boundary.

This =cdification would entail examinaticn and tests in accordance with the Construction Code & Section 7.I for this Class 3 System.

ALTERNAf E TESTING: The system is of a fixed resis tance for inservice testin2 of this purp.

All required test gr'.ntities except flew rate shall be reasured.

The dif ferential pressure shall be used co assist in dete rmining punp operability.

9)

SYSTE"-

Emergency Nuclear Service Seawater CJ"PONENTS:

E'4P-2 A an d R'i? -2 3 TEST DUANTITY:

Pi, inlet p re s s u re BASIS f or RELIEF: There is not a pressure tap installed in the discharge line af these pumps to reasure the inlet p re s s ure.

The installa-tice of e tap would require a modification of the pipe pres-sure boundar).

This nocification vould entail examinatica and tests in accordance with the Constructicn Code & Secticn XI for a Class 3 System.

ALTERNATF TESTING: Inlet pressure shall be calculated by tide level.

10)

SYSTEM:

Emergency Nuclear Service Seawater CC"PC';FNTS :

ON?-2 A and OSP-23 TEST CUA'; TIT'(:

Q, Ficw Ea t e k

,1 Ya

Page 4 of 4 TABLE B PU"? TEST P20 CRAM PZOUESTS FOR RELIEF 10)

Centinued:

B AS I S for RELIEF-The re is not a flev element installed in the discharge li.. e of these pumps to measure the flew rate.

The installatica of an element would require a medifi car ica of the pipe pres-sure boundary.

This modification eculd entail examinaticn and tests in 1ccordance with the Constructicn Code 5 Sectica XI for a Class 3 System.

ALTF RNATF TESTING:ihe system may be variable resistance for the inservice test of these pumps at a given time (i.e.: heat exchan,;e r out for maintenance or cleaning).

It will be attempted to fix the resistance of the systen during the performance of an inser-vice test o f th e p ump, though it may not be always passible.

If the system resistance is varied during the test, it shall be noted en the procedure.

Should a test quantity be out of norcal ran ge, it shall be evaluated on the basis of the var-ied resistance in the system, 11)

SY ST E S'.

Energency Diesel Generat ar Fuel Trans fer Purps COMPO E M :

DFP-1A ( AC Powe r Supply)

DFP-1B (AC Fower Supply)

DFP-lC (DC Power Supply)

DFP-lD (DC Pcwcr Supplv)

TEST GUANTITIES:

Pi, inlet pressure, p,

lifferential pressure, Q, Fl cw Ra t e,

V, Vib ratien Arplit ude,1 be arin g tenperature.

BASIS for EELIEF' The pumping recium of these pumps is diesel fuel. This sys-tem has been classified by the Cvner as Class 3 in accordance with the safety functicn to be pe rformed.

Secticn XI of the ASME Code was originally intended to tes c cr.ly these systers ccntaining water, steam, and radioactive was te c ont ainin g compenents in nuclear power plants.

The design basis of :he E=crgency Diesel Fuel Oil Transfer Purgs is such that each diesel has a separate AC purp power-ed fro: an essential bus and a separate a sckup DC pump pcwer-ed f rca vital scurces.

Additionally, there are provisions for tecporarily cross-tieing the systems t"gether and hand pumps if required.

ALTE RN AT TESTI'G: Zach diesel 2nd the respective diesel fuel oil transfer systen shall be tested in accordance with facility Technical Specificaticns. This surveillance shall incluce operatienal checks of the subject pumps.

The successful completien of this surveillance shall denote the subject purps satisfied their safety function.

The current Technical Specificaticas require each diesel be tested nenthly.

434 25:/

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F1b 30'8-O l l PAGE I of I P11EPARI:D BY S. W.

JOIINSON DATE 7/16/79 Revision 2 m

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TABLE 2A "ALVE RELIEF REQUEST BASIS Page 1.F1,

System: Main S te am (>$)

1.

valves:

5V-14 S and :3V-130.

Function; These are block valves outside containment to drain the secondarv side of the steam generator.

Test Requirement:

EF-1F Basis for Relief:

The valves are not used ductng normal plant operation and renain full closed.

S t rokin g them during normal plant operation would drain feedwater from the OTSG and create severe system upset transients.

Alternate Testiag:

EF-2F Thc ial+es shall be tested at cold shutdown.

2.

Val es:

MSV-411, 13V-412, >$ V-413, >GV-414 Function:

These are the main steam isolation valves which automatically close upon a main steam rupture matrix signal of 600 psig decreasing pressure.

Test Re quirement :

EF-lF Basis for Relie f:

A full stroke of these valves during normal operation would interrupt the flow o f ste nn t o the main turbine, resulting in the rain s te am reliefs lifting and a turbine / reactor trip.

Alternate Testing:

EF-lP, EF-2F.

These valves shall be part-stroked quarterly, full stroked at cold shut-down.

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TABLE 2 A VALVE FILIEF REQUEST B ASIS Page 1 of 1 System: Auxiliary Stean 1.

Valve:

ASV-50 Fut:ction :

Stea -driven erergency feedwater pump turbine (E FTB-1) overspeed trip and throt tle valve.

Test Requirement:

EF-lF Basis for Relie f:

Testing the overspeed tri Sf this valve requires c

manual manipulatica of the governor centrol en E FTB-1.

The more f requent the required interval of the test of this valve, the chances are increased inadve rt ent improper adjustment of the governor.

Improper adjustrent could prevent required quantity of emergency feedwater to the OTSC for safety opera-tien.

(The normal interval for testing the main turbine at this facility far overapeed protection sys tem is each refueling).

Alte rnate Testing:

EF-3F.

The overspeed trip of the EFT 3-1 will be tested at refueling.

2.

Valve:

ASV-23 Function:

This is the boundary valve between class 3 and quality-group D en the auxiliary steam system.

This allows EFTB-1 to be supplied from auxiliary steam header. However, this is a non-safety, ncn-semic back-up source o f s team to EFTB-1.

Test Re q uiremen t :

EF-lF Basis for Relief:

This valve is closed during normal plant cperatien.

A*txiliary s team is not a safety and seismic class source of power for the emergency feedwater turbine.

Alte rnate Testiag: Operational checks with appropriate record entries shall record the position of these passive valves before operaticas are perforced and af ter eperatices are completed.

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VAI.VES FOR UlllCll RI:1.lEF IS REQllESTED SYSTEf1 FLAME F F FD'OTF u

.IMG. NO.

FD-302-081 l' AGE _ _ ' ' of

l'l El'ARED IlY 4

W.

.10llNS ON DATE 7/16/74 Revision 2 m

f.c]

41 O

liASIS l'OR

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CATEGORY 43 H p'a al m

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2 EF-2F 8

FUV-41 2

C-1 FUV-4

C-3 X

6 CK SA 0

2 EF-2F 8

FWV-43 2

F-2 X

6 CK SA C

2 EF-2F S

g_

FWV-44 2

F-1 X

6 CK SA C

2 EF-2F 5

L J

A FUV-157 3

D-1 X

6 CK SA C

2 EF-2F 6

FUV-158 3

D-3 X

6 CK SA C

2 E F-2 F 6

N FUV-46 2

3-F X

18 CK SA O

7 L

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9 FWV-37 2

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10 Cl.

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10 Gl.

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.1 9

TABLE 2 A VALVE RELIEF REQUEST BASIS Page 1 of 5 Syscem: Feedwater (F.i) 1.

Valves:

FWV-29 and FMV-30 Functica:

"ain feedwater block valves for feedwater ccntrol during reactor power maneuvering and feedwater isolation en main stean rupture matrix sicnal.

Test Requirement:

EF-lF Basis f o r Re lie f :

Stroking of these valves at normal plant operation would result in a feedwater transient.

This would subject the plant t o an uns a fe condition and a potential reactor trip.

Alte rnate Testing:

EF-lP, EF-2F.

The valves shall be full stroked and tired at cold shutdown and part s troked eve re th re e

( 3) =anths.

2.

Valves:

F4V-31 and FWV-32 Functica:

These valves are the icw lead feedwater block valves.

When reactor pcwer is frem 151 to 100%, valves are full open.

Valves will close en main steam rupture mat rix signal.

Test Requirerent:

EF-lF Basis for Relief.

Full stroking of these valves during normal plcnt operatien would cause an upset in the feedwater control system by partial interruptica of required feedwater flow.

This sculd subj ect the plant to an unsafe ecnditien and a potential reactor trip.

Alte rnate Tes ting:

2F-lP, E F-2 F.

Those valves shall be part streked at three (3) tenth intervals, and full stroked and tired at cold shutdown.

3.

Valves:

FWV-33 and FWV-36 Function:

These valves are the startup feedwater block zalve; and are full open throughout all reacter pcwer operatien under norral cperating cenditicns.

E loss of all four (4) RC pumps or loss of bcth nain feedwate r pumps, the valves close to allow feedwater er emergency feedwater to t'..e CTSG thrcu?h the emer-gency feecwater nozzles.

'7alve s close en main steam rupture matriz signal.

Test Recuireman:

FF-l?

434 26}7

TABLE 2A VALVE RELIEF REQUEST 3 ASIS Page

of 5 System:

Fe e dwat e r ( ET',

1. 3 centinued.

3.

Basis tar Relief:

Full stroking of these valves during normal plant operation would cause a transient in the fcecwater control system by partial interruption of required feedwater ficw.

This would subject the plant to an unsafe ccnditien and a potential reactor trip.

Alt e rn at e Te s tin g:

EF-lP, EF-2F.

These valves shall be part strcked at three (3) = cath intervals and full stroked and tired at cold shutdown.

4

\\.alves:

-. \\.,, and ms.<-aa ra s-Functicn:

These valves are th e emergency feedwat er llech "alves and open en loss o f both main Ei p"tps or loss of all four (4) IC cumps to f u rnish r.,

threuth the emergency Ei nozzles of the OTSCs.

-1est t,e q u, re re n t :

-l-tr r

Basis for Relief.

The s treking of these valves during normal plant cperation would introduce feedwater through the eme rgen cy f eedwate r nozz l es en the OISGs.

This would caus e a transient in the main stea and feedwater centrol s:. s tems, subj ectin g the plant to an unsafe condition and a potential reactor trip.

The plant is not designed to operate in this anner under nerral conditions.

Valves cannot be part-stroked during nocnal plant cperation f c r s ame reascn.

Alte rnate Tes ting:

EF-2F The val.es shall be full streked and tined at cold shutdown.

J.

Valves:

E'4V-43 and EiV-4e Function:

Check valves outside containment on emergency reed-water line to OT3Gs for ccntainment isolatica cnd preventien o f baci: ficw in the line.

Valve is closed during normal plant cperaticn.

rest Requi re ren t :

EF-l?

3 asis for Relie f-The opening of these check '/alves aculd require a positive indication of ficw thrcugh the ene r gen cy feecwate r noncles c f the GT5Gs.

This caanot be dene durinc ncreal plant cperation as it would cause a transient in the main steam and reedwater to the Ct o.

tnis :culd subject the olant te unSaf0 CCndition.

The plant IS not designed to ope rat e in this Zanner under nor al acnditicrs o$7 f

TABLE 2A VALVE FILIEF PIQL'ESI BASIS Paze 3 o f 5_

Syste=:

Feedwate r ( P4) t/5 continued.

5.

Basis for Relief:

Testing these val'.es in the reverse f l e*.. direction would not increase safety as the feedwater system is a closed Icep and backup by block valves for isolation.

ilte rnate Ter tin g:

EF-2F.

Valves will be full strcked at cold s'aut-down for opening by ficw indicatien through emerguacy feedwater flow reter.

6.

Valves:

FWV-157 and FWV-153 Functicn:

ormally closed check zalves to prevent b a c 4 f i c.,

from cain feedwater to emergency fe:dwater piping.

Their safety function is to cpen for emerjency feedwater ficv to the OTSGs en Icss of both =ain feedwate r pumps.

Test T.e q uire re n t :

EF-1F Basis for Relief:

To insure that the cisks of these zal'.es cove off their seats requires a positive indication of ficw.

This cannot be achieved during normal plant cperation as it re q ui res injectic of cold crergency feedwater to the preheated main fee cwate r sys ter.

This would result in a transient in the main steam and feed-water centrol system, subjecting the plant to an unsafe conditica and a potential reactor trip.

7alves cannot be part s troked for same reasens during noraal plant operation.

Alte rnate Tes ting:

EF-2F.

Valve shall be full stroked during cold shutdowns.

,,a lve s :

ra.-43 an c; f

ra.

-e Functica:

These are the main feedwater systen centainrent isolation valves to prevent backflow.

During plant operatica thesc valves are cont inuous ly open aa 1cng as a rain feedwater purp is in operatien.

Test Requirement:

EF-lF Basis for Relief To insure that the disks of there valves nove to their seated positier open cessatien of feedwater fica cannot be accenplished eith present plant design.

These 16" checks do not hav_ external a se posit;:r indicators.

Other methods of testing coulc requirn ficoding or nit rogen p ressurication of the OT53 and cpening drains and ven ts up st ream o f the subject valves These "alves are cacced up b:. retar-cperat<

434 21949

TABLE 2A VALVE CILIEF REQIJEST BASIS Page 4 ef 5 Systen:

Fe e dwat e r ( Di) 47 continued.

7.

Basis f or Eclief:

block valves upstrea which are being tested.

Since the main feedwater systen is a closed loop system through the ccntainment with upstream bicck valves for backup, a re ve rs e flew check of these valves was not desi~ned into the systen.

Alte rnate Tes ting.

These valves are tested fer tull epening during normal plant operatica by proper rain feecwater flev being maintained in the OTSC.

Eclief is requested from a reverse ficw test.

. lves:

r.1,.. -41 anu, r.s.,.,-4.,

c.

a Fuaction:

During normal plant cperation these valves cpen to provic;e main Icecwater to tu..e U,T5o.

..tpen a pressure differentia' the valves close to prevent reve rs e flew, i.e. when ene rgency feedwater is initi-ated and main flow fec cwate r n. uno. s ara * '"c.ed.

The val'.as alse se rve as a sys ter boundary valve betweer a class 3 and quality-group D syst_r.

Test Ee q ui r e me n t :

EF-IF dasis for Felie f:

The test of these zalves fer clcsure upon cessatien of rain feedwite r f1cw requires an ex;ernal disk positica indicator on these 'alves or scre ork,r pesitive means o f ve rification.

The calves are net equipped eita disk positica indicators.

The other positive reans of icentificatica wculd require vent-in z and drainin ~ the syste: upstrear of the subiect e.,,

va ves wh,c.n is cenprtsee at-a large vo1ure c: o an d IS" p ipin g.

Alternate Testing:

. iile tes ting the erergency f eedwate r sys tem a t cold sautcewn, clesure c these valves shall be verified by prcper ficw of eterpency feedwater to the OTSG.

9.

Valves:

F4v-40, F.i;-39, F.iV '; 7, F4V-35

-iunction!

s..-39 an

• 'n

~inese ra r,. c a are used for start-a v

up feedwater flew control to 157; cf tull feedwater ficw.

'frer 15%, the valves are full cper F.i'.'- 3 7 and 39 -- These talves contral feedwater ficw during ics loud operatiens frca 15 to 507 feecwat e r cercnd.

Test 7equirem nta

..-11 4,

l' a%

m t

TABLE 2A VALVE REllEF REQUEST 3 ASIS Page 5 of 5 System:

Feedwate r (I'.?) :!9 centinuad.

9.

Basis for Relief.

These feedwater flow regulating valves are used throughout the normal plant cpe rating cycle.

Ans nalfunction of the.e valves would be identified innediately and corrective measures initiated.

A Section XI inservice rest far these cata cory 3 ealves in ac co rdance wi th I'.-:V-3410 dces no t add to the safety of this facility.

Alte rnate Te s ting:

During normal plant cperatica these ralves are being tested by prepe r f eecwater control.

Any degradatien or r.alfunction shall be evaluated at the time of detection and corrective reasures initiated.

T/.!111:

1.

VAINF.S I;EING TESTl:D IN AGG0!!DA:iCl: Ul Til Colic !!L l'II&? E ITb SY:;TEtl II A"E tm rm T :cy F 9T n',n T F it I f,lG. NO.

FD-502-082 l' AGE 1 of~ l l'REPAPED liY s

P.

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1 i:T-7

'these valves may he closed by EFV-32 3

A-S X

6 GA I1O O

1 El'-l l operator actien in case of l

1 1:T-8 rupture of an 1:FU 1ine down-z,trean of these valves.

't h e EFV-14 i

B-6 X

6 GA ML)

O 1

':F-l l '

c losing o f the:,e valves vould I

iET-?

allow the other. t ca"a generato to be f eed emer};ency leedwater lil'V- ! l 3

H-b X

b GA MO O

1

": F-1 1 and continue c oo l i ni; the it G 1

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li-6 X

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1 T-I F

T A!;!.l 2.

val.VI.S IliR Ull1 Cil PFf.I E F I S REQU ES'I E D SYSTEtt MA!!F E!f E RG E'lCY FEEL > WATER I f.l G. t:0 I'n m2 0 9' PAGE I of I l-REl'AT:ED 1:Y 9

W.

.loliNSON DATE 7/16/79 Revision 2 l

1 vi H

n c4 W

c II AS I S FOR y A;'yy' H

m

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d. [y 31 REll El, CATEGORY f"

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REFARFS I;UIllill.It g

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2 EF-2F 1

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H GA

!:0 C

2 EF-2F 1

1:T-7 N

1:FV-7 3

E-4 X

6 SCK SA C

2 EF-2F 2

NJ EFV-8 3

15 - 5 X

6

CK SA C

2 I:F-2F 2

EFV-5 3

C-5 X

4 CK SA C

1 EF-IP 4

2 EF-2F 1:FV-6 3

E-S X

4 CK SA C

1 E F-l l' 4

2 EF-2F 1:FV-15 3

A-7 6

CK SA C

2 EF-2F 3

1:FV-16 3

A-7 X

6 CK SA C

2 EF-2F 3

ElY-17 3

A-H X

6 CK SA C

2 EF-2F 3

1:1"!-l M 3

A-7 X

6 CK SA C

2 1:F-21 3

-.ntt,.,

ta

.r s t v r. Lirr. n r e< l. r2 i-, u Lc,

,r oc

..w Page 1 of 2 byste:

r ergency _

.eecuater 1.

e.alves:

E,i:..

u c.i

. r-e.

Fun c t icn :

Eme r;,e acy f eecwate r supply f rcr min ccncenser t o ete r;'ency f ee dwat e r p urp s.

D:ese are 5ickup ealves, only used if the cendensate stcrage tank becctes un avail ab le.

The ccadenser is a aca-seistic ncn-safety related syster.

-test Requirerent:

y _ - I..

r r

Basis fcr N lie:-

Tac valves are interlocked with the ccacenser vacuua b re ake rs to prevent inalzertent cpenia; with a condenser facuur.

T2stine during ner 11 cpe ratien 'eculd rec + n a "jurre r" to ccfeat in te rle ck.

Alte r at e Test:

EF-2F.

Valve s snall be full s trched and tired at cold shut dcwn.

mm.

v 4r_-

(.3 d> rre._s c.W

/ -

2

> a l.. a.

vu Functicn:

2 ese valses are the emergency f e e dua t e r p ump discharge s:cp check 'talves.

During normal plant operatica the

?. lve s are closed.

Test c'e q ui re me n t :

3:-lF Basis f or Re li. f.

To insure the valve disk cares off its seat requires indica *ica of ficw to the OTSG.

This cannot be dene durin? :orral plant cperaticn :s it would require f i c.. of cre rgency faecu rer to the OTSG thrauf' the emer ency feedwater noczles.

Tnis wculd cau;e a seve re transient in *he

.ain s tear and f eec.cate r cent rol sys tem, subjecting the plant to an unsafe condition.

ine,siant is not des! gned to cpe rate in this canner under mornal cpe rating conditions.

"...1.., 3,,,,s,. e,_ _ a.. _ e...,,, u. o. _ m... e, m._,.,..,.m.s, a

..o-2 durin.; normal plant croration.

4

3. A0.

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3.1 c,.1.4 u., u

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w cold ahutdcwn by ficw to the CTSG,

/l $s4 o

t. c.> L =-.,.a

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-- cr t.

Page 2 of 2 Sy a t.m EF 3.

a.,,u. c,..

-., -13, E,r 16, E,..,,.e,

.r. -,. - 1 q

~nnction:

Durin g no rmal plant cperatie. these 'ral res are c1csed providin g rain s tean p ressure isolation frca the

. re rgency : eedwat e r sy3 :er.

I'n e s a f e t :.

a function of the checks are to open to provide emergency feeeenter to the OT;G cn less of both rain feet' eate r purps.

<equired Tests:

EF-1F Basis for Reller.

To insure the valve disk cores off its seat requires indicaticr of ficw to ~5e CTSG.

This cannot be dcne during nor al plant et eratien as it would require ficw of emergenc:. feedeater ta the OU G throug.h the erergency t ee& eater nozzles.

This aonld cause a sc.e re tran.ient in the r.a i r stea and ;eedwater cantrol syster, subjectin_

the plant to.,

unsafe ccnditica.

The p1r.t is not de s i gr e ci to cperate in this rahaar

• nder nor-al operating conditicn3.

'Tals 2 s cannot b e r:' rt-s t rie d f o r s ame re :s ens during nor.al plunt aperation.

.il t e rn a t e T u t in.

E7-2 F.

Valves ahall be full stroked at cold shutdewn by ficw to the OTS0s.

e

.v., 1..., c..

r r. '.' _ a-u,.. A-p r..' _ ;)'

.t FunctiC"*

First Che Ch :/al.'le in a sericS of two at the lis-charge cf the erergency f eedwct e r purps uen are s

clcsed caring normal plant cperation.

Cpen ener-

izing the energe ncy reestater punos on Icss of both r.ain feedwate r pumps, the calves cren to pto-vide cooling,to the RC syster through the OTSU.

Test Re q ui re re n e.

EF-IF B as i., f o r f.e lie f :

Full strokc of this val'.2 eculd require e re r ce n cy fe e.raa t e r fi vx to the OTSG thr: ugh the en e rga.cy f e e dwa t eL. ne2Zlu' ThiS WGuld Cause 3 s e '. e. '

tra"Sient in the ~. ' i n S t e d 0.n '2 f ee dwat er Cont rol s:. s t e rs, aubjecti.; the plant to cn ensafe ::n-

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VAT.VES FOR UllICil RE!.IEF IS REQUESTED SYSTEtt flAftE DECAY llEAT ltEMOVAL DWG. 110, FD-10?-641 PAGE I of 2 PREPARED BY S.U.

.Tolit!SO?i DATE 7/16-79 Revision 2 m

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TABLE 2 A VALVE RELIEF REQt ?ST BASIS Page 1 of 4 System:

Decay Heat Removal 1.

Valves:

DRV-1 and DHV-2 Fun tion:

Puring nor=al plant cperation it is the second of two normally closed check valves to provide reactor coolant isolation frca the decay heat removal system.

The safety function of the valves are open to provide low pressure inject-icn or decay heat remov11 to the reactor core.

Test Req ui re ment :

EF-lF, SLT-2 Basis for Relief:

The opening of these valves requires a reverse dif ferential pressure which cannot. achieved during normal plant operatio.

Seat leakage tests for these valves by present design would be hazardous to test pe rs enne l due to high radiation. The seat leakage test requires the handling and/or collection of high pressure and temperature radioactive fluid which may flash to steam at the valve seat boundary during testing.

To test these valves would require the addi-tien of drain valves to a class 1 pressura b ounda ry.

Alte rnate Testing:

These valves shall be full stroked at cold shut-down by verification that 3000 gpn decay heat flow is passing throug'. the valves.

For verification that during normal plant oper-ation there is not leakage of RC system to the decay heat removal system pressure gauges shall be monitored daily downstream of low pressure injection discharge valves LHV-5 and CRV-6.

In addition, should seat leakage occur, relief capacity is provided through relief valves DHV-17 an d DHV-2 8 c r 31. 5 gp a e ach.

2.

Valves:

DHV

.0 and DHV-lll Function:

These valves prevent pump runout during 1cw p res s ure injectica by maintaining the decay heat removal (low pressure injection) pumps at ^000 gpr discharge flew.

)

TABLE 2 A VALVE RELIEF REQUEST BASIS Page 2 of 4 System:

Decay Heat Removal continued Test Require ment :

EF-lF Basis for Relie f:

These valves are not required to move from a full closed position to a full open (or con-versely) to fulfill their safety function.

The valves are normally full open, sensing no flow, and will throttle to maintain flow during system operability checks or LPI oper-ation. A full stroke and time test of these valves does not ine.rease the facility safety.

Alternate Testing:

These valves will be tested at the same fre-quency as system inservice operability checks for the decay heat removal system. The vilves shall be tested during these tests to assure that they maintain proper pump discharge < per-ability flow.

3.

Valve:

DRV-91 Function:

By operator actien, this valve and RCV-33 opens to cool down the pressurizer when the reactor coolant systen is in the design pres-sure limits of the decay heat removal sys tem.

Test Require ment s :

EF-lF Basis for Relief:

Stroking of this valve during normal plant operation would be potentially comprising the decay heat system by stroking a valve connect-ing a high pressure system to a low pressure system.

The valve has no safety function.

It is used for normal reactor shutdown.

Alternate Testing:

EF-2F.

Val re shall be stroked and timed at cold shutdova.

4.

Valve:

DHV-93 Function:

Closed valve during normal plant operation.

Opens to cool the pressurizer from the decay heat removal system when the reactor is in cooldown when the RC pressure is within design pressure limits of the decay heat removal system.

Test Requi rements :

EF-lF Basis for Relief:

Opening this valve is impossible during normal plant operation as the decay heat removal sys-tem is a lower pressure system than the RC system.

434 3;(

TABLE 2 A VALVE RELIEF REQUEST BASIS Pape 3 of 4 System:

Decay Heat Removal continued Alte rnate Testing:

EF-2F.

The valve shall be full stroked at cold shutdown with verificatien being a re-duction of RC temperature / pressure.

5.

Valves:

DHV-3 and DHV-4 Function:

Removal of decay heat from the reactor ves-sel during the decay heat mode of operation.

These valves are only used in the decay heat mode and not ESA mode.

Test Requi reten ts :

EF-1F, SLT-2 Basis for Relief:

The3e valves are not designed to be stroked during normai plant operatien.

Stroking the valves subject the low pressure DH piping to the high pressure PC system.

The valves also have an interlock to prevent opening with RC pressure greater than 284 psig.

Seat leakage tests for these valves by present design would be hazacdous to test personnel due to '.1gh radiation. The seat leakage test re-quires the handling and/or c allection of high pressure and temperature radioactive fluid which may flash ta steam at the valve seat boundary during testing.

To test these valves would require the addi-tion of drain valves to a class 1 pressure b o unda ry.

Alternate Testing:

TF-2F.

Valves shall be full stroked and timed at cold shutdown.

A pressure gage shall be installed downstream of DHV-3 and 4 The gage shall be monitored weekly for increasing pressure, which would denote laakage of DHV-3 anu 4.

Should esces-sive leakage occur, corrective action shall be initiated.

6.

Valves:

DHV-9 and CHV-10 Function:

Decay heat discharge valves to the borated water atorage tank for pump operability checks.

Valves:

DHV-105 and DHV-106

.hf$

TABLE 2A VALVE RELIEF REQUEST BASIS Page 4 of 4 Systeu:

Decay Heat Removal continued Function:

Decay heat pump discharge isolation valves to the make up and purification pre-filters.

The valves ar.. used during shutdown for RC system

" cleanup." Not required for normal or safety shuc3cwn functiens.

Valves:

DHV-75 and DHV-76 Function:

Re. urn line to the decay heat pucp suction from the makeup system filtars.

Used during shutdown for RC system " cleanup."

Test Requirc=ent:

EF-lF Basis for Relief:

These are passive valves not required to change position to fulfill their function for normal or safety reactor shutdown.

Alte rnate Tes ting:

Operational checks with appropriate record entries shall record the position of these passive valves before operati ens are performed and after operations are completed.

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TABLE 2A VALVE RELIEF REQUEST BASIS Page 1 of 3 Systea:

Reactor Coolant (RC) 1.

Valve:

RCV-53 Function:

By operator action, this valve opens to.ool down the pressurizer when the reactor cocla..t system is in the design pressure limit of the decay heat removal sys tem.

Test Requiremen t :

EF-lF, 6LT-2 Basis for Relief:

Stroking this valve during normal plant oper-ation would be potentially comprising the de-cay heat sys tem by s troking a valve from a h19.,. essure sys tem connecting to a low pres-sure system.

The valve has no safe ty function.

It is used for normal reactor shutdown.

Seat leakage tests for these valves by present design would be hazardous to test pe rs onnel due to high radiation.

The seat leakage test requires the handling and/or :711ection of high pressure and temperature radioactive fluid which may flash to steam at the valve seat boundary during tes ting.

To test this valve would require che addition of drain valves to a class 1 pressure boundary.

The downstream decay heat valves, DHV-93 and DHV-91, are being Appendix J type seat leak tested.

In addition, should RCV-53, RCV-12, DHV-9 3 and DHV-91 all concurrently leak, the integrity of the decay heat system would be protected by relief valve DEV-17, which has a relief capacity of 31.5 GFM.

Alternate Testing:

EF-2F.

Valve shall be stroked and timed at cold shutdown.

No alternate seat leak testing.

2.

Valve:

RCV-12 Function:

This valve is closed during normal plant oper-ation.

Opens to cool the pressurizer f rom the decay hear removal system when the reactor is in cool down and RC pressure is within design pressure limits of decay heat removal system.

k bl l

TABLE 2 A VALVE RELIEF REQUEST BASIS Page 3 of 3 System:

Reactor Coolant continued Basis for Relief:

facility.

Pressure regulating valves are continued specifica1.ly excluded from testing by Section XI, 1977 Edition through Su==er 1978 Addenda, IWV-1200(a).

(This addenda is non-mandatory at this facility.)

Alternate Testing:

During normal plant operation this valve is being continuously tested by maintaining the RC pressure sat point.

Any malfunction in the valve will be evaluated at the time of detection and corrective action initiated.

4.

Valve:

RCV-13 Function:

This valve is the isolation block salve for the pressurizer spray valve.

Test Requirement :

EF-1 Basis for Relief:

This valve is normally open.

Stroking this valve during normal plant operation affects the design tethod of controlling RC pressure.

This could result in a reactor trip and poten-tial unsafe plant condition.

Alternate Testing:

EF-2F.

Valve shall be full strokea and ti=ed at cold shutdown.

TABLE 1.

VALVES -BEI!1G TESTED Iti ACCOIWA'4CE WITil CODE REQUIREtiE?iTS SYSTE!! II At!E

?!AKElIP & PURIFICATIOri IMG. 11 0.

FD-30 2 -661 PACE 1 ot'2, 7/16/79 Pilt'ARED BY _

9.

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TAlll.E 2.

VALVES BEING TESTED IN ACCORDA!1CE WITil CODE REQUIREF1ENTS t!AKEUP & PURIFICATION 2 of M SYSTEtt liA!!E

, JXJG. NO.

FD-302-661 PAGE PREPARED 111 S_ U.

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TABLE 2 A VALVE RELIEF REQUEST BASIS Page 1 of 8 System:

Make-up and Purification 1.

Va2res:

MUV-42, MUV-37 Function:

These valves are the first of two closed valves to prevent reverse flea from the RC system to the MU system. Their s afety func-tion is to open to provide HPI to the RC system.

Valves:

MUV-160, ML'V-16 3, MUV-164 runction:

These valves are th( ' mond of two closed valves to prevent reverse flow to the SW system fron the RC system. Their sa %ty function is to op.n to provide HPI to the RC Lystem.

Test Requiremen t :

EF-1, SLT-2 Basis fn. Relie f :

In order to part stroke or full stroke these valves during norual plant operation it would require injection of MU water (approximately 90 to 100

• F) through the HPI nozzles.

CR-3 Technical Specifications, Section 5.0, Design Basis, p. 5-8, (Technical Specification Change Request Number 37 dated 3/21/79) limits de-sign cycle transients to 40 cycles on the HPI system.

Full or part stroke of these valves during normal plant cperation constitutes a cycle transient.

The r c f o re, testing at 3 month periods shall co= promise this system leading to potential damage of the HPI nozzles.

The piping upstream of these valves is rated at a higher pressure than RC system pressure.

Therefore seat leakage is not i=p o rt ant for these valves.

Pressure gauges shall be installed at the down-stream side of the HPI discharge valves (MUV-23, 25 and 26).

This gauge shall be monitored for leakage through the two dcuns tream check valves prior to stroking the HPI valves.

Should excess leakage occur from the downstrcam check valves (i.e. MUV-42 and MUV-160; MUV-36 and MUV-163; MUV-37 and MUV-164) corrective

=casures shall be initiated.

This should eli-minate water hacmer concerns.

434 32j/

TABLE 2A VALVE RELIEF FIQUEST BASIS Page 2 of 8 System-Make-up and Purification continued Alternate Testing:

These valves shall be tested at cold shutdown for full scroking.

Full stroke will be veri-fied throudt flow elements to each HPI cold leg in RC system.

No alternate seat leak test.

2.

Valve:

MUV-43 Function :

This valve is the first of two partially open valves which provides makeup to the RC system.

The valve opens to provide HP1 to the RC system in the ESA mode.

Valve:

>TV-161 Function:

This valve is the second of two partially open valves which provides makeup to the RC system. The valve opens to provide HPI to the RC system in the ESA mode.

Test Re quire =ent :

EF-lF Basis for Relief:

These check valves are part stroked opened during normal plant operation.

This is veri-fled through the =akeup injection ficw, i.e.

pressurizer level control.

Full stroke of these valves at normal plant operation would require injection of makeup to the RC system.

This would result in a pressurizer level rise virtually uncontrolled, subjecting the plant to a potentially unsafe condition.

Alternate Testing:

The valve will be tested at cold shutdown for full s trokin g.

Full stroke verified by flow elements in EPI line to RCS.

3.

Valves:

MUV-10, MUV-6, MUV-2 Function:

These are stopcheck valves to prevent pump run-out and prevent backflow upon pressure differ-ential to the suction side of the MU pu=ps.

Valves:

MUV-1, MUV-7, MUV-ll Function:

These are the first check valve-on the dis-charge of the MU pumps. These will prevent backflow upon pressure differential to the suction side of the FM pumps.

434 32g

TABLE 2A VALVE RELIEF REQUEST BASIS Page 3 of 8 Sys tem:

fake-cp and Purification continued Test Require ments :

EF-lF Basis for Relief:

Stroking these valves would require injecting HPI into the RC system.

This could cause a potentially unsafe plant condition as design control of pressurizer level is lost.

HPI nozzles are limited to 40 thermal transients by technical specifications, Section 50, Design Basis.

(See Table 2 A, Number 1, Make up and Purification System of this relief request.)

Alternate Testings:

EF-1P, EF-2 F.

These valves shall be part streked during MU system operability checks (currently conthly) and full s troked at cold shutdown.

Full stroke verification will be by flow through the HPI leg.

4.

Valve:

MUV-18 Function:

Block valve outside containment for isolation of RC pump seal injection.

Test Require ment :

EF-lF basis for Relief:

Stroking this valve would interrupt seal in-jection flow to the RC pump seal package, re-sulting in potential damage to the seals.

Durir.3 accider2 conditions the valve will re-main open for seal cooling from the HPI (MU) p umps.

These get no ES signal. Valves are not designed for part stroking.

Alternate Testing:

EF-2F.

Valve shall be f all stroked and timed at cold shutdown.

5.

Valve:

MUV-27 Function:

Normal make up isolation block valve to reactor coolant system.

Test Require ment :

EF-lF Basis for Relief:

Should this valve stick in the closed position during a full Ltroke during normal plant oper-ation, the normal means of pressurizer level control is removed. This could cause a poten-tial unsafe plant condition.

Valve is oc*. de-signed fc r part stroking.

TABLE 2A VALVE RELIEF REQUEST BASIS Page 4 of -

System:

>bke up and Purification continued Alternate Testing:

EF-2F.

Valve shall be full stroked and timed during cold shutdown.

6.

Valve:

MUV-49 Function:

T atdown cooler isolation block valve out-side containment.

All RC system letdown passes through this valve.

Test Require ments :

EF-lF Basis for Relief:

Should this valve fail in the closed posi-tion while stroking during normal plant oper-ation, RC system letdown capabilities would be lost.

RC pu=p seal injection cannot be t e rminated.

The plant would have to be trip-ped en high pressurizer level.

Valves are not designed for partial stroking.

Alternate Testing:

E F-2 F.

Valve to be stroked and timed at cold shutdown.

7.

Valves:

MUV-253 (outside containment) ; MUV-258, "UV-259, MUV-260, MUV-261 (inside containcent)

Function:

Controlled bleedof f of reactor coolant pump seals containment isolation valves.

Test Requirement :

EF-lF Basis for Relief:

Should any of these valves fail in the closed position while full stroking in normal plant operation, the design mode of normal controlled bleedoff of one gpm of the RC pump seal would be lost. This could lead to seal degradation and possibly preme are RC pu=p seal failure.

Seal replacement is a high manrem exposure maintenance item.

Valves are not desi gned for partial stroking.

Alternate Testing:

EF-2F.

Valves shall be full-stroked and timed at cold shutdown. MUV-253 and MUV-259 shal' be part stroked at least once every 3 montb:,

8.

Valve:

MUV-16 Function:

Reactor coolant pump seal injection control valve for seal injection.

TABLE 2A VALVE RELIEF REQUEST BASIS Page 5 of 8 System:

Make up and Purification continued Valve:

MUV-31 Function:

Controls the pressurizer level by the amount of makeup admitted to the RC system through tha valve.

Test Requirement :

EF-lF Basis for Relief:

These valves are being calibrated on a yearly basis with the related inJ trument s tring.

During normal plant operation these valves are in continuous use and any malfunction would be immediately noted.

Corrective action would be initiated i= mediately.

An inservice test per Section XI requirements does not add to the safety of this facility.

Alternate Testing:

Valves are in continuous use and any malfunc-tion or degradation will be noted and correc-tive action initiated.

Valves M-53 and MUV-25 7 Function:

MU pump minimum flow recirculation valves.

Test Requirements :

EF-1F Basis for Relief:

The stroking of these valves during normal plant operation would interrupt mini =um re-circulation flow on the running makeup pump.

Should the valve fail in the closed position, damage would result to the makeup (high pres-sure injection) pu=p.

Alternate Testing:

E F-2 F.

Valves will be stroked and tired at cold shutdown.

9.

Valve:

MUV-30 Function:

Manual bypass around pressurizer level control valve (MUV-31).

Valve:

MUV-17 Function:

Manual bypass around RC pu=p seal injection controller (MUV-16).

Test Requirement:

EF-lF tl a% p

.z s

TABLE 2A VALVE RELIEF REQUEST %\\ SIS Page 6 of 8 System:

Make up and Purification continued Basis for Relief:

Full stroking of these valves during normal plant operation would be subjecting the plant to a potential transient of the pressurizer level control system and RC pump seal injec-tion flow control valves. While stroking MUV-30 and MUV-17, their respective control valves would have to compensate for this additional flow.

If a transient occurred during the exercising, automatic control is not in effect.

These valves are located in a high radiation zone unere loc 91 hot spots in excess of 100 mrem / hour exist.

Alternate Testing:

EF-2F.

Valves shall be full stroked at cold shutdc. <:.

10.

Valve:

MUV-64 Function:

Makeup tank isolation valve for the ESI do of operation. The valre is opened during

=al plant operation an.' closes on an ESA sig-nal.

Tes t Require =ent:

EF-lF Basis for Relief:

The closing of this valve during normal plant operation would isolate the makeup tank from the makeup pu=p suction, cut ting of f the make-up flow to the pump, resulting in damage to safety related equipment.

Alternate Testing:

EF-2F.

The valve shall be stroked and timed at cold shunicvn.

11.

Valve:

MUV-65 Function:

During t.ormal plant operation this check valve is opened for suction supply to the makeup pumps from the meteup tanl.

Upon a pressure differential these valves should close to iso-late the MUT from the BWST.

This function would occur in the ESA mode.

Test Requirement :

EF-Ir Basis for Relief:

Testing of this valve during normal plant op-eration would require a reverse pressure

}

TABLE 2A VALVE RELIEF REQUEST BASIS Page 7 of 8 System:

Make up and Purification continued differential across the valve, thus isola-tion of the makeup pump f rom the makeup tank.

This would result in damage to the makeup (HPI) pump.

Alternate Testing:

EF-2F.

This valve shall be tested for closure at cold shutdown.

Evidence of proper disc seating shall be no increasing level in the makeup tank with BWST head pressure downstream of valve.

12.

Valves:

imV-266, FmV-264, FNV-147 Fun ction :

Makeup pumps lA, 1B and 1C rceirculation block valves at th e p umps.

Valve:

MUV-5 Function:

Manual control valve used to fill the coreflood tank from the makeup system.

Test Requirement :

EF-lF Basis for Relief:

These are passive valves not required to change position for normal or safety shutdcwn of the reactor.

Alternate Testing:

Operational checks with appropriate record entries shall record the positten of these passive valves before operations are performed and after operations are completed.

13.

Valve:

MUV-108 Function:

Used to control the rate and amount of addition of boric acid, demineralized water, or water from the RC bleed tanks to the RC system through the makeup system.

Test Req airements :

EF-lF Basis for Relief:

The valve is used frequently during normal plant operation.

Any degradation or malfunction of the valve would be evident during the course of plant operation.

A full stroke of this valve in accordance with Section XI requirements does not increase the safety of this facility

TAB LE 2 A VALVE RELIEF REQUEST BnSIS Page 8 of 8 System:

Make up and Purificatten continued Alternate Testing:

The valve is in frequent use during normal plan t operation in accordance with its f un e -

tian.

Upon detection of valve degradation, corrective measures shall be initiated. The manual bypass, MUV-158, shall be tested in accordance with Section XI.

14.

Valve:

MUV-51 Fun ction:

Pypass valve around block orifice on RC system letdown line to the makeup and purification system.

Test Requirement :

EF-lF Basis for Relief:

This velve is used frequently during normal operation to increase letdown flow.

Any degradation or malfunction of the valve would be evident and evaluated at time of discove y.

Tne testing of this valve in accordance with Section XI requirements does not increase the safety of this f acility.

Alternate Testing:

The valve is in f requent use during normal plant operation in accordance with its func-tion.

Ccrrective measures will be init '.sted at the time of discovery of any val w de-gradation.

15.

Valves:

MUV-72 and MUV-60 Fun ction :

These valves are normally closed during normal plant operation.

Upon initiation of HFI, they open for BWST supply to the HPI pumps.

Upon depletion of the BWST and changing to RB sump recirculation, the valves close by operator action to prevent backflow to the BWST HPI discharge valves.

Test Req ui rements :

EF-lF Basis for Relief:

A full stroke of these valves require HPI flow at " safety function" conditions to the RC system.

This cannot be done during normal plant operations.

Alternete Testing:

EF-2F.

The valves snall be full stroked at cold shutdown by verification of required flow to the ECS.

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TABLE 2 A VALVE RELIEF REQUEST BASIS Page 1 of 1 System:

Chemical Addition 1.

'.'alve :

CAV-61 Function:

Thi.s check valve is closed during normal plant operation. The valve opens upon emergency injection of boric acid to the RC system through the Makeup and Purification System.

The line bypasses the normal injection mode through the batch control valve OUV-108).

Basis for Relief:

A full stroke of this valve during normal plant operation would require an uncontrolled injection of boric acid into the RC system through the nor-mal makeup system.

This uncontrolled injection would effect reactivity control if proper boron concentration is not maintained. This would require either a reduction of reactor power or a control rod adjustment to compensate for the reactivity change. The results of these would be an increase in radiation waste or possibly control rod placement outside of the rod index curve, respectively.

Alternate Testing:

EF-lP, EF-2F.

The valve shall be part stroked quarterly and full stroked at cold shutdown.

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TABI.E 1.

VAI.VES IlEltlG TESTED lli AC00ltDAllCE WITil CODE REQUIREMEllTS SYSTEtt liA!!E I.TOUID WASTE DISPOS AI.

IMG. 11 0.

FD.ig2-681 P AGE 1_nf, 1 PREPARED bY

9. U.

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B-4 X

3 DA A

C 1

BF-1F 2740 ESA Signc.1:

RB Isolation 1

l:F-5 3

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li-4 X

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'i LT-1 WDV-61 2

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2 A

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VALVES llEING TESTED Ill ACCORDANCE WITli CODE REQUIREFfENTS g,

CONTAINMENT F10NITORING SYSTEFI IMG. NO.

FD-302-691 PAGE 1 of 1

//16/79 PREPARED BY s.W.

101tN90N DATE Revision 2 l

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X 1

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OC-1 1370 3

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0 1

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EF-5 1

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WSV-4 2

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TAPLE 1.

VALVES Bell 1G TESTED lll ACColtDAllCE WITil CODE IU:QUIREMEllTS SYSTEll ll A!!E

0RE FLOODING

&,. 11 0.

FD-302-709 PAGC 1 of 2 7/16 '79 PREPARED BY S.U..lO!!N90N DAiE Revision 2 va l

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iLT-1 I

T A!!I.E 1.

val,VES lil:Ifi? TESTED til ACCORlWICE WITil CODE REQUll(EllEllTS SYSTEM tlAf!E CORE FIGODING I)W G. fl0 -

Fn-109-700 l' AGE 1 of 2 7/16/79

'ARED BY S. U.

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TABLE 2A VALVE RELIFF REQUEST BASIS Page_1 of 3 System:

Core Flood 1.

Valvas:

CFV-2 and CFV-4 Funct ion:

This is the second of two normally closed check valves which provides RC isola'. ion from core flood tank.

The valves open af ter a large RC rupture has occurred to provide cooling to the reactor core by water from the core flood tank.

Test Re quirement :

EF-lF, SLT-2 Basis fcr Relief:

In order to full stroke this valve it would re-quire simulating a large RC rupture in which RC pressure decreases rapidly to saturation pres-sure for the RC temperature.

This simulation is impossible for full stroking these valves during normal plant ope rat ion.

A part stroke of these valves at cold shutdown would require removing a quantity of core flood volume with a high boric acid concentration into the RC syste n as this would increase the radioactive waste co deborate the RC system.

Seat leakage tests for these valves by present design would be hazardous to test personnel due to high radiation. The seat leakage test re-quires the handling and/or :ollection of high pressure :,M temperature rai.iation fluid which may flash to steam at the valva seat bcundary during tes ting.

To test these valves would require the additien of drain valves to a class 1 pressure bouncary.

Alternate Testing:

EF-3F, SLT-2.

Ac refueling these valves shall 4e part-stroked by causing a reverse dif ferential pressure a-cross the valves for opening.

Part stroke chall be confirmed by a decreasing core flood tank level and an increasing pressurizer level.

During normal plant operation, the core flood tank pressure and level shall be monitored each shift to assure no leakage through the valve combinations of CFV-1 and CFV-3 or CFV-2 and CFV-4 The boric aci6 concentration of the core flood tank shall be monitored conthly to verify correct concentration to assure no dilution occurs during operation, i.e.

RC system back leakage to the CF tank.

3 f

TABLE 2A VALVE RELlEF REQUEST BASIS Page 2 of 3 System:

Core Flood continued Core flood system inventory can be controlled through the blowdown and sampling line.

Level and pressure instrumentation with high alar =s are on the core flood tanks.

Relief capacity is provided by safety relief valves CFV-23 and CFV-24 of 1288 cfm of air or 3978 lbs/hr.

saturated steam.

2.

Valves:

CFV-1 and CFV-3 Function:

These are the first of two normally closed check valves which provides reactor coolant isolation from the decay heat and core flood sys te ms. These valves open to pro ~ide decay heat cooling, low pressure injection, or core flood water to the reactor core.

Test Req uirament :

EF-lF, SLT-2 Basis for Relief:

The opening of these ralves requires a reverse dif ferential pressure that cannot be achieved by any method during norma] plant operation.

Seat leakage tests for these valves by present design would be hazardous to test personnel cue to high radiation.

The seat leakage test re-quires the handling and/or collection of high pressure and temperature radioactive fluid which may flash to steam at the valve seat boundary during testing.

To test these valves would require the addition of drain valves to a class 1 pressure boundary.

Alternate resting:

EF-2 F, EF-3P, SLT-2 These valv..s shall be full stroked at cold shut-down by verification that 3000 gpm decay heat flow is flowing through the valves.

At refueling the valves shall be part stroked by causing a reverse dif ferential pressure a-cross the valves for opening.

Part stroke shall be confirmed by a decreasing core flood tank level and an increasing pressurizer level.

TABLE 2A VALVE RELIEF REQUEST BASIS Page 3 of 3 System:

Core Flo,d cantinued Dur_tg normal plant operation the core flood tank pressure shall be monitored each shift to assure no leakage through the valve combi-nations of CFV-1 and CFV-3 or CFV-2 and CFV-4.

The boric acid concentration of the core flood tank shall be monitored monthly to verify cor-rect cencentration to assure no dilution occurs during operation, i.e. RC system br.ck leakage to the CF tank.

Core Flcod System inventory can be controlled through the blowdown and sampling lines.

Level and pressure instrumentation with high alarrs are on the core flood tanks.

Relief capacity is provided by safety relief valves CFV-23 and CFV-24 of 1288 cfm of air or 3978 lbs/hr.

saturated steam.

3.

Valves:

CFV-lP and CFV-19 Function:

Provide building isolation, valve opens to allow filling of the CF tank from the MU pumps.

Test Requirement:

EF-lF Basis for Relief:

Normally there is not a reason to add makeup to the CF tank during normal operations or cold shutdown except to makeup for sampling losses.

Alternate Testing:

EF-3F.

When makeup is added to the core flood tank, appropriate entries with procedures shall verify operation of these valves.

These valves shall be full stroked each refueling when fil-ling the CF tank after the CF tank test.

434 34197'

TAlil.E 1.

val.VES llEltlG TESTED lli ACC0!!DAtlCE UlTil C01)E REQUIREMEllTS SYSTEll fl AllE REAcr0R BUILDINT SPRAY IMG. [10.

FD-302-711 PAGF _1_nf 1 7/16/79 PitEPARED BY s.U..follt190fl DATE 1(e v i s i on 2 m

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BSV-3o 2

B-5 X

4 GA M

LO 1

OC-1 LN

+N-BSV-4 2

E-3 X

8 GL 110 C

1 EF-lF ES A Signal: Open on IG Isolation 1

BT-6 ESV-3 2

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1 F:F-1 ESA Signal: Open on RB Isolation 1

BT-6 BSV-8 2

E-7 X

10 CK SA 1

F:F-lF BSV-1 2

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1 EF-lF ESA Signal: Open on RB Isolation 1

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1 1:F-lF ESA Signal: Open on RB Isolation 1

BT-7 "i-99 2

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TABLE 2A VALVE RELIEF REQUEST BASIS Page 1 of 2 System:

Building Spray 1.

Valves:

BSV-37 and BSV-36 Function:

On an RB isolation signal, these valves open and the sodium hyatoxide begins mixing with the borated water from the BWST through the HP1 and LPI systems in anticipation of a 30 paig signal on high RB pressure. The sodium hydroxide raises the pH of the borated water to assist in the chemical stability of iodine, a post accident radionuclide.

Test Requirement :

EF-lF Basis for Relief:

A full stroke of these valves would introduce sodium hydroxide into the LPI system.

Should the valve fail in the open position, the sodium hydroxide would infiltrate the LPI and BWST.

This could lead to sodium hydroxide in the HPI system and possibly the RC system. A chemical " clean-up" of the systems would be necessary.

This would mean additional radia-tion waste and make the piping more susceptible to caus tic cracking.

Should the sodium enter the RCS, it could lead to additional man-rem exposure by activation of the sodium-24.

During cold shutdown, the decay heat (LPI) system is in use.

A sttche of the valve could introduce sodium hydroxide in the borated wate" system.

This could increase unit down time to perform a system cleanup and have chemically damaging effect on safety components.

Alternate Testing:

EF-3F.

The subject valves shall be r uked and timed each refueling.

2.

Valves:

BSV-152 and BSV-153 Function:

These are normally closed valves that prevent reverse flow to the sodium hydroy.ide tank from the BWST.

They must open to allow sodium hy-droxide to gravity feed to the borated water system on RB isolation signal (4 psig RB pressure).

Test Requirement :

EF-lF

TABLE 2A VALVE RELIEF REQUEST BASIS Page 2 of 2 System:

Building Spray continued Basis for Relief:

Part or full stroke of thase valves would re-quire introduction of the high caustic solu-tion of sodium hydroxide into the borated water system.

Th a d.tsase ably of these valves withot: flushing and draining would be a severe safety hazard to personnel.

There exists no zethod for flushing or draining of these valves.

A'.t ernate Testing:

There presently is no method for part or full stroke of these valves under any plant condi-tion.

The proolem is under consideration by the f acility's engineering s taf f.

No alter-nate tes ting.

3.

Valves:

BSV-26 and BSV-27 Function:

Normally closed valves which open for contain-ment building cooling on 30 psig RB pressure signal which initiates the building spray p umps.

Test Requi.ement:

EF-lF Basis for Relief:

The full stroke of thesa valves would re-quire initiation of the RB spray sys tem.

This would entail spraying the RB with bor-ated water.

Alternate Testing:

These valves shall be disassembled and in-spected once each inspection period (40 months).

The inspection shall assure that the disks have freedom of motion and Jeter-m ne the general mechanical condition of the valve including presence of any loose parts, deb ris, abnormal corrosion products, wear and erosion.

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TAB LE 2 A VALVE RELIEF REQUEST BASIS Page 3 nr 3 System:

Chilled Water 1.

'7alves :

CHV-56, GIV-57, OlV-5 8, GIV-59, CHV-60, CHV-61, CHV-6 2, CHV-6 3.

Fun ction.

These valves control chilled water flow for penetration (AHEE 13A & 13B), Control complex

( AHHE-5A & SB) and switchgear room ( AHF-16A

& B) cooling by discharge temperature.

Valves:

CHV-68, CHV-69 Function:

These valves controls the flow of nuclear service closed cycle cooling water to the chiller (CHHE-1A & 1B) by Test Requirement:

EF-lF Basis for Relief:

These va] res are being calibrated on a yearly basis with the related ins trument string.

During normal plant operation these valves are in continuous use and any ralfunction would be immediately ao.2d.

Cctrective action would be initiated. An inservi:e test per Section XI requirements does not add to the safety of this facility.

Alternate Testir.g:

Valves are in continuous use and any mal-function or degradation will be noted and corractive action initiated.

2.

Valves:

CHV-48, CHV-49, CHV-50, CHV-51 Function:

These manual butterfly valves are used for balancing flow between penetration cooling

( AHHE-13A & B) and control complex cooling

'AHHE-5A & SB).

Test Requirement:

EF-1F Basis for Relief ?

These valves are manually set to balance flows through their respective heat exchangers and do not change position during normal or emergency operation.

Alternate Testing:

Valves are used for system operating conven-ience therefore no testing is required per AS} E Section XI.

434 35fji