ML19350E199
| ML19350E199 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 06/15/1981 |
| From: | Novarro J LONG ISLAND LIGHTING CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| GL-81-04, GL-81-4, SNRC-582, NUDOCS 8106170134 | |
| Download: ML19350E199 (66) | |
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- LONG ISLAND LIGHTING COM PANY
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__Lauramrwas SHOREHAM NUCLEAR POWER STATION l 1
P.O. BOX S18. NORTH COUNTRY ROAD + WADING RIVER. N.Y.11792 l l
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June 15, 1981 SNRC-582 g
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Mr. Harold R. Denton, Director 97h,t 8tys,it, 60gyr ! h
~~
Office of Nuclear Reactor Regulation ~~
U. S. Nuclear Regulatory Commission 300 1 G **# J2 Washington, D. C. 20555 % o.s.4% ,
Shoreham Nuclear Power Station - Unit 1
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Docket No. 50-322
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Dear Mr. Denton:
Enclosed herewith are sixty (60) copies of our response to NRC Generic Letter 81-04.* Attachments 1 and 2 are being forwarded herewith. Attachment 3 was forwarded in our response to SER Open Item No. 60 via SNRC-577 dated May 27, 1981, and is also included with this submittal for your convenience. Attachment 1,
" Loss of AC Power", provides a description of the Shareham transmission and power distribution system and actions for power restoration. Attachment 2, " Station Blackout Analysis",
describes the actions necessary and equipment available to main-tain the reactor coolant inventory and heat removal capability with only D.C. power available. Attachment 3 addresses the issue of " Station Blackout" and confirms that emergency procedures will be developed to ensure safe operation of the plant and restoration of A.C. power. In addition, operators will be trained to effectively deal with this event as indicated by our commitment to perform several tests verifying RCIC operability under degraded electrical conditions as part of the low power test program.
Also enclosed are sixty (60) copies of our " Management Survey",
which was developed based on the review by your staff of our response to SER Open Item #52.
With regard to your evaluation of brittle fracture of containment boundary materials, a copy of mill test reports and associated dccumentation for an outboard Main Steam Isolation Valve was hand-delivered to your staff by our 1r. J. P. Mori on June 12, 1981.
Refer to NRC letter from Mr. Darrel G. Eisenhut to All Licensees cf Operating Nuclear Pcwer Reactors and Applicants for Operating Licenses, dated February 25, 1981, regarding Emergency Procedures and Training for Station Blackout Events.
8306170/M4 [
FC.893 5
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Mr. H. R. Denten June 15, 1981 RE: SER Open Items Page 2 If you require additional information or clarification, please do not hesitate to contact this office.
yours, V,ery)trul li /
,_-h ,'- d 'g211 f
{,J.P.Nofarro Project Manager Shoreham Nuclear Power Station RWG:mh Enclosures cc: J. Higgins 5
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Attachment 1 y LOSS OF AC POWER (including DC System Reliability) s (Reference FSAR Chapter 8.0) d t
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- 1. Shoreham Switchyards 4 P
o Electric power generated at the Shoreham Station is transformed F from generator voltage to a 138KV transmission system voltage W by the main power transformers. The main power transformers .,
are connected via steel transmission poles to the station 138KV y switchyard consisting of circuit breakers, disconnect switches, [,
busses support structures and associated relay protection F equipment as shown in Figure I. i Four 138KV overhead lines exit the switchyard on two separate'
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rights-of-way and connect to the 138KV grid at Holbrook,
- Brookhaven and Wildwood substations. .
a.
The station 138KV switchyard busses are continuously energized h and serve as the preferred power source for the station safety M loads. Two physically independent lines are provided to the $
Plant from the 138 & 69 KV switchyards. Two system auxiliary' y transformers step tha nominal 138 & 69KV voltages down to the f, station 4160 volt power system busses.. This configuration -
t provides the availability of redundant sources of offsite power. pp.
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- 2. A.C. Power Distribution System - ..
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^ The ECCS systems at the Shoreham station are separated into [
three redundant and independent subsystems known as Divisions $
,.f 2, II, & III (Figure III). The alternating current auxiliaries k
" - to each of these divisions are powered from 4160 volt busses
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identified as Bus 101, Bus 102 and Bus 103.respectively. The g T' Jd0 volt auxiliaries and 120 volt control circuits are fed - '
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from their respective 4160 volt busses. There are no inter- g connections between any redundant AC power supplies at the 1 4160, 480 or 120 volt AC levels, thereby maintaining their '
k independence as required by criterion IL . .
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~S The 4160 volt busses 101, 102 and 103 which are assigned to. . ,
ECCS Divisions I, II 6 III respectively have, as their primary' -
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source of offsite power, a connection to the 138KV switchyard- ' >
'&': via overhead transmission line from-the Normal Station Service' R
'5 7.. ' Transformer (NSST). Their backup offsite connection is from , ,. ~
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the 69KV switchyard (Figure II) via underground cable from the [. / . '
'"IM Reserve Station Service Transformer., Each of these 4160 voltc~ ; ' ' ;
IE'.? " ' busses has its own dedicated. diesel generator as its outside % F -
3 SI:41 - source of AC power.* * * " "'M' W '
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!L 2-m Loss of Division I AC power supplies will result in the full i or partial loss of the following critical equipment. I r
- a. Partial loss of RER A loop. tI ',
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- b. Total loss of core spray A loop. E 3
- c. Partial loss of service water system loop A.
- d. Partial loss of the Reactor Building Standby '
- Ventilation System (RBSVS) and.the Control L Room Air Conditioning (CRAC) water chilling p
- system.
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- e. Partial loss of the control rod drive water pumping b system. ~
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- f. Partial loss of Reactor Building Closed Loop Cooling [
Water (RBCLCW) A loop. , b:
Under postulated accident conditions their functions would be b performed by redundant equipment in Divisions II & III. 1 e.;
h Loss of Division II AC power supplies will result in full or '
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partial loss of the following critical equipment: - -
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- a. Partial loss of RER B loop. ' - -
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. d Total loss of core spray 3 loop.,.' ] >
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- c. Partial loss of service water system loop B. $
~ d. Partial loss of RBSVS & CRAC water chilling.. L system. - -
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- . 's. Partial loss of control rod drive water pumping system.
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,- Under postulated accident conditions their functions would be
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'.77 Loss of Division III AC power supplies w'111' result,in the partial 3 t-R/;r i3ydEN r , .
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- e. Partial loss of RBCLCW I, oops A and B. Lf l
Under postulated accident conditions their functions would be ({:I u performed by redundant equipment in Divisions I & II. !.3
- 3. D.C. On Site Power System -
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- The D.C. onsite power system for the Shoreham station consists l of of thethe others:following sybsystems each of which is fully independent ,
a
- b. 125 V - D.C. subsystem (ECCS Div II) Fig. V il1 c.
125 V - D.C. subsystem (ECCS Div III and non ECCS) Fig. VI _ L d. 125 V - D.C. subsystem (non ECCS - Balance of Plant) !g e. 125 V - D.C. subsystem (non ECCS - Balance of Plant) ,'
- f. .125 V - D.C. subsystem (non ECCS - Communications 4 -
1 Security 'l;, \.!
Monitoring Systems' Fig. VII hj
i. p 24 V - D.C. sybsystem (non ECCS - Ra31ation & Neutron , Monitoring Systems) Fig. VII L 125 V D.C. sybsystems associated with ECCS Division I, II & III w 6 do not have any interconnections with each other i b y The 24 V - D.C. batueries are connected to provide + 24 D.C. i-r power to the radiation and neutron monitoring systeiiis and auxiliary trip devices. i l Two ,+ 24 V D.C. systems are provided, , , u ~ -. m.: w M y : m. . { - The three 125 V D.C. subsystems supplying non-ess,en_tial loads - . _ i P~ are required to provide control power to the balance of plant y 3 Qv' D.c systems. One of these 125 V D.'C. subsystems supplies uninterrup ;-- ,,' W:.? table power to the station communication and security systems. . .. 2
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- 4. The Action for Restoring Offsite AC Power in the Event of a Loss of the-Grid I^ '
All LILCO fossil fuel fired plants have onsite black start M) capability. In addition LILCO has black start capability i l gas turbines throughout the system (Holbrook, Southhold, { y Southhampton, Barrett, East Hampton and West Babylon) and M diesel black start capability at Buell.and Montauk substa- i? tions. In case of a complete system shutdown the system power dispatcher would restore the system to ncrmal in as short a time as possible by re-energizing the transmission @l e network in a sequence which would vary with prevailing con- j? ditions at the time of the blackout. Auxiliary power will T be restored to Shoreham on a priority. basis. [ t. . Restoration of the auxiliary power supply to the Shoraham N plant is expected to be accomplished by black start of the W Holbrook station and restoration of the 138 KV lines between .. Holbrook and the Shoreham 13BKV switchyard. This will restore , one of the preferred sources to the Shorehas plant in less j than 30 minutes provided there is no damage to transmission ' facilities. The second preferred offsite source will be - restored by energizing the Shoreham 69KV switchyard via the [, Wildwood 138/69 KV transformer. Energization of the Shoreham _. 69KV switchya.rd will provide starting power to the Shoreham )/, 55 MW gas turbine which is located in the -69KV switchyard. [i This will provide the plant with a reliable on-site source of- ~j . power. . ?' y There are eight gas turbine driven generators on the LILCO E system with black start capability, any one of which is capable F of supplying the total **nargency power requirements of the Shoreham plant. , _- - S) ,- O. Time required to restore the Shoreham auxiliary offsite power supply will vary with the nature of the grid blackout and the j'
- i er %nt of any associated damage to the transmission lines. j The total system restoration is expected to be completed within J a day. As an example, the LILCO system restoration time after y the 1965 blackout was less than 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and many system improve- i..
ments have been added since that time. . m L _. ;, 6.k.R S-- p A less extensive grid disturbance could isolate the Shoreham station with total loss of offsite power through the unlikely- n simultaneous outage of all four transmission lines, i.e., . f" one to Holbrook, one, to Wildwood /Riverhead, one to Brookhaven k ?- and one to Wildwood (69KV) . In such an event, the restoration > time of any one line would vary considerably with the extent' - -? of the damage associated with the outage. . Outage. time could, . J +, vary anywhere from an hour-;to several days.'p-6jggg" . - [ .~.y'. . 3
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~ M#ec-M &e$ttg A &i&WW h eW'^k;% - ~ ,a ._ n . _ .m. - . .. l , W -s-- T For those incidents in which suustantial damage is done to 4, transmission structures tempora y repair measures are possible. y The Company has had an emergency restoration plan (ERP1 in e effect for over thirty-five years. Under this plan emergency material kits for transmission repairs are maintained at several 1!, locations including Riverhead which is approximately eleven D miles from the Shoreham station; , Rag'11ar LILCO crews are trained and equipped to carry out the repairs. [ Jl i<
- 5. The Actions for Restoring Offsite AC Power When its Loss is Due to Postulated Onsite Equipment failures
[, 11 The most severe credible failure of onsite equipment resulting ;; in loss of offsite AC power is a tornado causing the outage 1? of the entire 138 and 69 W switchyards at Shoreham. The res- ,i toration actions and time would depend greatly on the type and extent of damage. Assuming such an event damaged both auxiliary 9 transformers (NSST & RSST), replacement transformers could be moved into place within seven days for the NSST and eight days ;.y for the RSST using existing spare transformers. Temporary wood ,2l pole construction could be used to connect to the nearest 138 1; or 69 W line. By focusing line repair efforts on a single 1 line, temporary repairs could be completed within the sevsn or eight day period or less. the emergency restoration plan (ERP) described in preceding The repairs would be made under [H yl Part 4. - . a-If the urgency of plant conditions require restoration -of y the offsite power in a shorter period of time a temporary .1: mobile unit transformer could be moved into place adjacent J to the RSST. This unit would be supplied with a temporary 69 W wood pole line from the 69 W switchyard and the output f. of the mobile transformer would be temporarily spliced into y the station 4160 volt overhead bus duct. This could be 1 accomplished in less than 7 days. . r r I e ,, s ,,,,j% . . g ~;~_.-:; - u s;$ m .c.;W ;.~, 2 =g ,[. '" ..) ., :p7;h T.-J
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,. y '~ q . -i'34a_ _ _ , i' 3 .(7: y .s) -l..; 'l i tt s l !'l . l "i . I j ' l . .}' 1l g' i Yil. t '!' d 1 l' } l '- j ' j' f . I .I'i'l t i r l l'i ! .; , ! i i ; 1 4.* i l ' .: r j ' ' i c < . . b 'l 1 l. l ; . , 1 -- - ; } } -j , i i ! ; , ; i ' 's ; } -l .i i -i. g.-t. ] j ' j ? 4 , a . C .l'.rj E { lj' ' j , s '.j .j . j ;.' i? ' t ! ! ! 1.} 1: .} . d ' i . d i l led .1 1 ' h%l .111 - i i { j i p,w! M j - i - l ! i ; i > i t ! ! t 1 -4 .-l.1 J 1 < I S al .~t P.N l t - 0 M:"! - -i I !~l t i u t$?W "b Y* 'k b b *l I$ n-Y $ ' ~' _ _ _ _ , _ _ , . _ _ m -m -- ., 7 Attachment 2 ATATION BLACKOUT ANALYSIS _ h The loss of off-site AC power and the three independent 3500 j'! kw diesel generators used to supply emergency power to the ~ st.ation constitutes the term " Station Blackout". This is not part of the design basis for Shoreham, No single event j together with a single failure would result in a Station y Blackout. The scenario presented below identifies those $ actions available to the operator to maintain control of ?; the station while AC power is being restored. - t The equipment available following this event is identz.fied in FSAR Table 8.3.2-1. A course of action has been identified ' { which will resulf in maintaining core and containment integrity for approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the initiating event. At I that time, the reactor will be depressurized and the contain- , ment will be at or below its design pressure and temperature limits. ( There are three large sources of water; the Condensate Storage , Tank (capacity 550,000 gallons) , the suppression Pool (.574,794 , gallons at low level), and 2 fire pump storage tanks (capacity l 300,000 gallons each). There ore three non-AC powered pumps: ' I the High Pressure Coolant Injection Pump (HPCI, capacity of h 4250 gpm), the Reactor Core Isolation. Cooling pump (RCIC, capacity of 400 gpm) , and the fire- pump (capacity of 2500 gpm) . The , fire pump is diesel driven while the HPCI and RCIC pumps are i '. turbine driven. The flow rates for the HPCI and RCIC pu n s are for either low or high pressure conditions in the reactor. A ' bar graph of equipment operation over the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.is presented in Figure I, and a description follows. y a At time zero, with loss of all AC power and no emergency diesels, Lj the reactor vessel will be isolated and thereafter lose feed-
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maintain pressure within RPV limits as the decay heat, fuel ( stored energy, and any remaining fission power generate steam. L Within tbs firct minute inventory loss will cause the water , :11 level to reach 12. The HPCI and RCIC systems will both start Pji at this level, initially taking suction from the condensate N Storage. Tank. .Pc 'l systems are designed to trip at LB and d restart at L2. ft is assumed that the operator will attempt to maintain water level between L2 and LB by throttling the.. HPCI turbine.- - , f,.: .m- w . h;..m, ,y.r N.;% m s, u. .w? g . f(H f It will take approximately four minutes to fill the vessel from J. L2 to L8 the first time the systems are called upon. . After this, . E it will take nearly twenty minutes, with some relief valve action, h i to again lower the water level to L2. Therefore, if the operator . 4
- chooses not to control water level during the first fill by thrott- 1 ling HPCI and turning off RCIC, he should be in a position-to accomplish this following the second initiation at L2, because.the
{p" .i . .%; j. y2::2):; .. . steam generation rate is ,lower. 3 g @ g.ag ,f l y.QC .. .a.pyy:;.;,.;.9 g M d L..g- ' ( . h5 - . w? .~ & D hY l , ' hg h , ,,s. . 8- * - , ' ** , l S k $ Alld ? b & W $ $ N 5 E b M 5 5 N $ $ $ ? S $ v: . r 2- E a At this time, the operator would align the fire water protection . system to connect to the tube side of the RHR HX's, and arrange '! the plant valves to go into the steam condensing mode of RHR. )'l Thias takes steam from the HPCI turbine steam line, and condenses it O i in the HX. The heat exchanger outflow, however, would be routed t $ to the suppression pool. The RCIC system would tako suction from i- l the suppression pool and pump it into the RPV. jl ,, 1 After approximately one hour and ten minutes from the initiating event, this mode of operation should be able to handle the decay heat generated. At that time, HPCI could be turned off, while
- j()
the fire pump and RCIC system remain activated. The diesel has (- enough fuel for eight hours of operation, with refill capability O. readily available. ' All non-essential loads will be shed from the station batteries. ). With the loads specified in FSAR Table 8.3.2-1, they are designed dj to last two hours. However, if RCIC is operated in a steady mode ?' and the RCIC condenser vacuum pump load is removed the batteries should last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. [ After approximately five hours of operation in this RER steam + condensing mode the fire storage tanks would have been drained. '. At this time the operator will commence reducing reactor pressure 4' to maintain RPV pressure below the point at which the suppression y pool heat capacity limit would be exceeded. Continued operation ': is then maintained using RCIC in its RPV low pressure mode using H.- CST water first, and then switching to the suppression pool water. $ V After approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the' initiating event, the contain- }. ment will be pressurized to its design point. If plant AC power i has not been restored by this time, some arrangement to supply [? water through the refilled fire protection system into the RPV C directly may be devised through the use of the well water pump or a fire truck which could pump water either from the fire hydrant I( near the plant access road or from Long Island Sound to the reactor building / fire storage tanks. i 3 ..- - N .. . g . F i .{ A' ~ ' u-
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) Ak N g N w=I - N0 @Mk'd J Mj'iL8' ' rem'.hhe#M' MI.O*.[f*v7u a %:a n,YNN = 4:d r v'}'#*$ N'**< 3 ]m/?,'M(.'",'M %.mw% ffh*MaytMh4+Q M w ~j am Z . .n Np+.s --%w'f;f $ *Q.',} Nlv'[v ".i < - __.__..__.m . .. . - - i I . F' - Attachment.3 t. If ~ SNPS Item 4 60 - Station Blackout . 2 c M In the very unlikely event that both offsite and onsite I ,7 alternating current (AC) power is lost, boiling water f-reactors may use a combination of safety / relief valves g-and the Reactor Core Isolation Cooling (RCIC) system to ~;. remove core decay heat without reliance on AC power. Emergency procedures will be developed to ensure safe operation of the plant and restoration of AC power. In addition, operators will be trained to effectively deal ; with this event. In this light, LILCO intends to perform, as part of its low power test program, several tests 6 verifying RCIC operability upon loss of AC power or other 3-degraded electrical conditions. For more details, refer to our response to NUREG-0737 item 2.G.1,
- Training During [g Low Power TestinT'. f a=
The procedures and most of the training described above will . u: be completed prior to fuel load. Completion of training (low power testing) can not be accomplished until after fuel i : load (but prior to commercial operation). c.j l A complete assessment of LILCO's planned facility procedures d, and training programs with respect to this matter will be forwarded by June 5, 1981. This is in accordance with the 4 ;j : letter from Darrel G. Eisenhut to all Licensees of Operating in Nuclear Power Reactors and Applicants for Operating Licenses y dated February 25, 1981 and received by LILCO on March 6, 1981, J.~ A g - y.. 3, pi f. n;; -; .. gi ~- .. . k ~ T{ y e I* . , , .E e . ,% *
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).,, v:.f3 . : ,.: a s - * '-*'s..'. _ ' J f , .; c. 'jyjgf.?, ' @t[ i,; , . ;-, .,'l 0 '. l. ' f. .' -~- w* ~ k.#.c ,- ..me- .;-.;b.a ,. bh:. w.yp;. x .ea. . mq,,.: .r, .y. w v.* 0y *.u. w-l:. b .f4 a ' i * ~ , 'r_ s l _, . ,'f * , ? ' .h a $. * ~ . r g y g .;.u:. m .u.;.. ,. . . ../- . . . . . . ! hy;4fidFG6MM444G.MkM. e/qefLh'M6MMg$64Mh8 TNNd$5wew%442RS2irC ~~ ~ x __.m. . m _ _ __ , ca. _ _2 u - t I $ e coh * - h - i' The following is a clarification to the LILCO response to NUREG 0737, item I.A.1.1. Personnel & Training The STA function will be performed initially by six (6) recintly graduated engineers. These personnel will be full time members of the Plant Staff. The educational back-grounds of these personnel are: three (3) - BSME one (1) - BSEE . two (2) - BEME . six (6) , The six designated STA's do not presently possess significant nuclear or work expe- . rience. The STA training program, which the six candidates must complete prior to assuming the STA duties, is designed to provide entry level engineers with a back-ground which dill be sufficient in a technical and in a practiE.a~1 sense to perform their assigned safety functions. The training program is scheduled to provide all the above STA candidates with the nuclear plant experience recor. emended ,in the INPO Training and Education publication, "Reconsmandations for Shift Technical Advisor", of April 1981. The Shoreham STA Training program and the FIA training schedule j are outlined in the report, "Shoreham Shift Technical Advisor Training Program" . 'Ihis report was provided to Mr. J. Schnell of USNRC on May 21, 1981. I To compensate for attrition and to facilitate scheduling, provisions have been made to train' backup STA's. Seven (7) engineer level members of the Plant Staff have been designated as backup STA's and*will receive tr=4ning to enable these personnel to competently perform the STA functions. The educational backgrounds l l of the seven backup STA's are: ' f Ie i 1 3 y .
- M '
e . .T $ p 8r de r , M c' i -
- BS Radiation Health Physics
- BS.ChEng + MSNE.' -
- BS Physics + MSNE -
- BSNE + MSNE
- BEE + MBA
- BSME ,
- BSEPE + MEEPE The seven designated backup STA candidates possess various levels of work and nuclear related experience, and each candidate will possess the nuclear plant experience re-commended by INPO prior to assuming duties as S"\. ,
The backup STA's will complete the same basic training program required of the six pritary STA candidates except , that port' ions of that program may be waived based on the Backup STA candidates work and academic records. All waivers for Backup STA candidates and the reasons for granting that waiver will 'be stipulated in writing. Thetargetkualificationdate for the seven Backup STA's is twelve months after fuel load. ~ Qualification as STA is awarded to those candidates who succes. fully complete the STA training program. The STA training program was developed in accordance with the effective NUREG documents, INPO recommendations, and the action of similiar operating units. An Item by item comparison of the Shoreham STA training program Cinclud:ng minimal educational requirements for candidacy) to the INPO recommendations indicates that the qualified Shoreham STA's will meet or exceed all INPO experience, training, and' education recommendations with the exception of training in the areas of materials and electrical sciences. STA Responsibilities i The primary duties of the STA are to -assess unusual, transient, or accident situations, to monitor vital plant parameters during an accident situation, and to advise the l , I 1 , S 'Q'l g , g ):,, ,. !S2hhb ,? 5 A h hh h k bs: n *N N **N'b5 : A S S' O ,I' t.*atch Engine:r in cvsiding and mitignting recctor damago. Csilatcral dutics which would interfere with performance of the STA's primary duties will not be assigned. l A secondary duty that thte STA vill normally assume is the function of the on-shift j nuclear engineer. By serving as the nuclear engineer, the STA would have an imme-diate and first hand knowledge of the. status of the plant, of reactor core behavior, and of the situation and the activities which may have preceded an emergency. This j should substantially enhance the STA's ability to evaluate the situation and to make appropriate recovery action recommendations. When not on shif t as STA, these personnel will be assigned various duties as appro- k priate to enhance their professional development, to improve overall plant safety and performance, and to provide meaningful and rewarding work. The six primary ? STA's will be assigned duties such as:
- evaluation of plant procedures from a safety viewpoint
- evaluation of plant procedures regarding effectiveness in terminating or in mitigating accidents .
- review Licensee Event Reports for applicability as assigned and provide an engineering evaluation of t.he LER's as necessary ,
- periodically review plant procedures for effectiveness ,
- conduct special investigations and prepare special reports as assignad
- act as a member of the On-site. Safety Review Group, a subcommittee of o 4
ROC, in accordance with NUREG 0737 I.B.l.2. (for off-shif t STA functions) Backup STA's will perform their regularly assigned engineering duties when not performing the STA function. f STA Organizat' ion The STA's will be independent of operations control. STA's (including backup j STA's when on duty) report administratively to the Reactor Engineer. j i h l 1 l l wnu-w mu-aman.- ..-----m .a " . . -- a .- . ~ . a _ - .- -a . sa; , . a ,x _ ,. , 0 5 s - . . . u . p . . F t r . The Reactor Engineer reports to the Chief Technical Engineer who is independent ,{. and equal to the Chief Operating Engineer, but is responsible for technical support -. g. . ;h; rather than production activities. Through this organization, the STA's can remain t v.p ')'l), functionally independent of production pressures below the level of Plant Manager. f
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e P O t o . 0-e * . * = , t g 1 == . C 1 b 9 . l i h l l t 3 l - . E \ ~ ?fk'??$W 4 . (~ ~* r INITIAL & REPLACEMENT SHIFr MANNING PROGRAM SIMfARY [ a - O Pre-Fuel Load Fuel Load Fuel Lc:d + 3 Mos. Fuel Load + 12 Mos. Fuci Load + 24 Mos. (1) (2) (3) (4) f-g ,, f i " u . i *i i i . p . u u . " u . " u y g= = g= a y = = g = g = Fv g.1* H "Fel !Em 1 s ( i .5 % %
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"l1 1 #m 1= 4 1 A 1 5 3 1 'a 1 A j i %n.R0 a % n ". R y n a . R - % n R M % n ". 'n m eaMoas< es t sdMo M 8 s s a M o a 2 s M a .5 x o M" t s a w M o <# @ iie ii i i e a e i 1 i e i : : : i # -en 4 m ~~m 4 m - ~ n 4 m - ~ n 4 m - ~ n 4 m : 4 f 1 k f 0 6 0 6 5 6 6 i f, Shift Supervisor 6 6 1 6 0 5 6 6 6 0 5 6 6 6- 0 5 6 6 i S;nier Reactor Operator 0 6 0 6 6 10 1 5 6 6 10 0 5 6 6 10 4 5 6 6 9 3 5 6 '6 - 11 ! ) Reretor Operator 01801218 14 5101218 14 0 10 .12 22 18 6 10 12 13 10 2 10 12 12 I' n I $ Equipment Operator 0 22 0 18 22 0 6 101219 NA 6 10 12 18 NA 6 10 12 11 NA 5 10 12 18 k 9 Shift Technical Advisor 0 6 0 NA NA NA 7 4 6 6 NA 7 4 6 6 NA 0 4 6 13 NA 0 4 6 13 l. HP/RC Technicians NA 0 NA 5 11 NA 0 NA 5 11 NA 0 NA 5 11 NA 0 NA 5 11 NA 0 NA 5 11 ! 7 g f GENERAL NOTE: A) 30% Rate for Exam Failure and Attrition for Operations Personnel. 8 I B) Five (5) individuals per shift position provides total shift coverage and vacation, sickness, . l' retirement, unexpected absences, etc. ' Four (4) individuals per shift position provides ; f>; adequate shift coverage. The desired level of six (6) individuals per shif t provides total I L shift coverage, combined vacation, sickness, etc. coverage, and a complete training program. I d L i i i- ? 4 k .g , -t , g] i 'g7 -'~ ~ ' ' I .a . . n . _ . _c.__.w . J. _... ;. L. __,_.a..___ n _ ._, .m. . . . _ . _ . . . . 11 ., = . , ll (l l -l ALDITIONAL NOTES ' FOR PREVIOUS TABLE j !l
- 1. (1)'SS (1) SRO Lost to Exam Failure, (1) SRO Promoted to SS ;I (6) R0 License at SRO Level - Of remaining (12) R0 (3) Lost to Exam Failure
and (1) Lost to Attrition of (1)) SRO Licenses (4) Available to function at RO Level (9) EO Take RO. Exam - (2) EO Fail Exam and (1) EO Lost to Attrition (6) EO Licensed at RO Level available to Function at R0 Level (6) New EO Hired
- 2. (1) SS (1) SRO Pass SRO Make-up Exam (1) SS (1) SRO Lost to Attrition (4) of (5) RO in training Pass Hake-up RO Exam (1) RO Exam Failure Available to to Function at EO Level (4) of (10) SRO Available to Function at RO Level, (0) RO Attrition (2) EO Lost to Attrition
- 3. (1) SS (1) SRO Lost to Attrition, (1) SRO (In Training for 4 mos.) Promoted to SS (1) RO Promoted to SRO (3) SRO Available to Function at R0 Level (3) R0 Lost to Attrition (4) RO Placed in SRO Training (1) RO Available to Function at EO Level (1) EO Lost to Attrition (6) EO Placed in RO Training (6) New EO Hired
- 4. (1) SS (1) SRO Lost to Attrition, (1) SRO (In Training 'for 4 mos.) Promoted to SS f (3) of (4) R0 Pass SRO Exam (1) RO Exam Failure - Remaina In SRO Training 5 (4) of (10) SRO Available to Function at RO Level
. (2) RO Lost to Attrition, (2) of (4) EO Pass RO Exam (2) EO Exam Failure Remain . In RO Training (2) RO Placed In SRO Training (1) EO Lost to Attrition (5) New EO Hired . 1 i, e % = ? .I ____________-_k ~ --
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t . o , I SSER #3 Staffing Resources he attached organization chart for Plant Staff represents our at and after fuel load staffing levels including attrition capabilities. Thus, the higher number of personnel than committed to in the FSAR. , I The xxxxx ectries are present vacancies, thus reflecting our prior to fuel load f status. The attached graph reflects our plans to add personnel over the period of time to fuel load. The NED and NOSD organization charts, given to Mr. Rivenbark, during the audit are our planned at fuel load complements. l The area of Training is somewhat different than on the chart in that we are bidding a training contract to provide at least four personnel to " flesh" out l the organization and supply personnel in addition if LILCO cannot " flesh" out ! the organs.tation shown on the chart. i 4 i s e 4 o e + W A X , 4 A a 1 .,r . ~ . . .L.'.~. ..L.- -~ .. + 8 m h -- . . . - . . .. ., , e -,0. - ,J.Cm.m,m. m . om. , PLAWT EsmeCER t g* j J. Asesale I G . W e e e - e a , , e e .e . e . , [ e . cette weta*tec cater treastcat. eerutwc ouatte' , " f* ". cet t *=? N uTE EUs.aget gun. au n 6 J. Caname aex wa 6 g 6 gege, . s t @ + A= ** Pef e e. e
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>l:I ,I b) 1li!l!1 ,j l! 1i . - - :- . . .: :- ,u . a . .. :....- . . . Il SSER NRC #4 J LILCO is currently preparing a tabulation of training and operational experience for all appropriate Corporate and Plant Staff Personnel. This tabulation will include identification of " hands-on" experience. Upon completion, this tabula-tion will be submitted for NRC review. I d M H N 1 s m b --_u . 5 - _k '- _ _ _ __Wr YN N0S' - $l f; 4 . . t' . i ~ SSER Item #5_ . As previously noted to NRC Staff, LILCO management has complete confidence in the ability and experience level of Shoreham's operations personnel to operate the unit in a safe and reliable manner. - In order to more clearly identify our competence to operate Shoreham, LILCO is providing a tabulation of all training and operational experience of corporate and plant staff personnel. In addition, LILCO has already made provisions with our NSSS supplier to have technical assistance available to the shift crew during startup. Over and above this commitment, LILCO shall provide through contract with General Electric.and other consultants, one " experienced, previously licensed" individual on each shift available to the Watch Engineer to provide technical support and direction. This additional experienced individual will also be , available to the Vice President-Nuclear for consultation. . e e G . $* e a 9 O O i j i I l e 1 ~ i 1 9 l l _,A , ' h' W { o
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SUBJECT:
Comparison of Onsite Technical Support Activities at Shoreham with ' NUREG-0731 Guidelines. The requirements of NUREG-0731 for Plant Staff Personnel Resources cover manage-ment, professional-technical, shift technical advisor, shift crews, and technician- ! i maintenance resources. The reference to onsite technical support in '.his sec- t tion is in the professional-technical resources paragraph (2b) which, in addition to the usual station departments, calls for " general engineering support" - no description.
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k The guidelines for the offsite support of routine operations changes corporate ) management to assure that an adeqizate saf.ety standard for the operation and maintenance of the plant is established. "To these ends eac[t license shall esta-blish an organization, parts of which shall be located onsite, to: I i
- 1. Perform independent reviews and surveillance of plant activities.
- 2. Provide technical support to the plant staff for maintenance, modifications, l
operational problems, and operational analysis. l I ( l The underlining is added for emphasis. No distinction was given in this section
- i or other sections on which technical support functions should be located onsite !
or offsite. However, it is stated that the license shall establish an integrated crganizational structure to provide for the overall management and technical support of plant operations. I i i I,n the paragraph covering offsite technical Staff Resources the following functions shall be provided to support the plant staff: am o
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- 1. Review of operating abnormalities. . l
- 2. Review of plant system problems and performance. [,
- 3. Review and correction of equipment malfunction.
- 4. Perform plant design changes and modifications or oversee such activities in detail in the event outside contracters are utilized.
- 5. Support major maintenance effects.
- 6. Evaluate and provide response to NRC bulletins and orders.
- 7. Establish and monitor contracted work.
- 8. Establish training, security, and emergency plans.
~~
Except for item 8, these activities have been delegated to the Shoreham onsite technical suppore group by the plant manager to the extent that manpower can support them. Requests for additional help or expertise can be provided by the l offsite groups, and in some cases, there is an overlap of activity responsibilit7 between the onsite and offsite groups. Technical capability of the offsite groups is to be provided in all the usual engineering disciplines in addition to health physics, fueling, operations, maintenance, quality assurance, and fire protection. Training anu qualification requirements for technical support personnel are out-lined in ANSI 3.2 and Regulatory Guide 1.8. the training for offsite support per-I sonnel is directed to aid these people in keeping current in health physics pro-cedures and in their func*. ions within the emergency response organization. Although NUREG-0731 describes a representative utility organization, the document admits that a single nuclear unit utility would probably not have the resources to establish separate organizational units for all areas shown. A-comparis-a-Of-the U 4echnieni-support-organization,-both onsite -and offulic, is the guidelines appears to be very favorableTrich,the.,possible exception _o ire-prerectionAMF ** se yg n l
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Basis for the Reportibility of the Operational Quality Assurance Engineer to the Plant Manager ANSI Standard 3.2 draft 5 of August 1980 and NUREG-0731 are quite clear in that the onsite quality assurance organization reports to the plant manager. The following statements are quoted from ANSI Std. 3.2, paragraph 3.4.2 Require-ments for the Onsite Operating Organization: a) The Plant Manager shall have overall responsibility for the execution of the i administrative controls and quality assurance program at the plant to assure safety. b) The individual or organization unit may report functionally to onsite plant management or an offsite organization. Reporting to onsite plant management usually results in improved communications in identifying problems and initia-ting corrective action. c) The individual or organization unit shall report on the effectiveness of the ] H program to the Plant Manager and to other cognizant management as may be de- ij signated. Their activities shall be periodically audited )y designated off-site personnel. NUREG-0731 lists Quality Assurance as a support function in section 2b under Plant Staff Personnel Resources.
- Figure 1 - Representative Plant Organization shows Quality Assurance reporting to plant management. l l
In paragraph A.1 Plant Staff Organization it is clearly stated, however, that the ! reporting of the functional areas of radiation protection, quality assurance, and training should assure independence from operating pressurqs. Ws ' %5 9 9 % n b ;:2 K Ud O E M M 2iG W NAdEi%dUNEh % :.. S.t%%Su:SE%Nhi?
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L. The proposed revision to the FSAR of Section 17.2.1 Quality Assurance During the Operations Phase - Orgartization assigns overall responsibility for the implementation i of the LILCO QA Program within the station to the Plant Manager and requires that he maintain lines of communication, coordination, and cooperation with the QA -k Manager. . fs Both the NRC and LILCO management recognize the need for the OQA Engineer and his s staff to report administrative 1y to plant management as the best method of organiza- ; a tion. j
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. June 5, 1981 -
To: . Re: Coup 11ance with NUREG-0731, " Guidelines for Utility Management Structure and Technical Resources ; Section III of NUREG-0731 addresses the management and technical resources required for accident mitigation and recovery efforts. The period of accident mitigation extends from the time an emergency condition is perceived to exist until the plant is brought under control. At Shoreham, the Watch Engineer, who is on duty at all
; times, is the individual who is in the inmediate onsite position of authority who has responsibility for safe plant operation. The Watch Engineer is responsible for the initial evaluation of any abnormal or emergency conditions and for initiating appropriate response efforts.
Section III-A of NUREG-0731, describes the o'nsite post-accident organization necessary to cope with an emergency situation. The SNPS Emergency Organization j , provides management personnel assigned responsibility for specific functions. The i resources and activities of the onsite emergency organizations are d2 scribed in l detail in the Shoreham Nuclear Power Station " Emergency Plan" Section 5.2 dated May 1981, and in the Emergency Plan Implementing Procedures (EPIP) SP 69.001.01, ~
" Emergency Organizations".
Section III-B of NUREG-0731 details the plans needed to assure the necessary j management and technical resources to support the onsite staff in the event of an l . accident. LILCO plans to use a combination of its own personnel and contractors to provide these off-site resources and activities. The SNPS " Emergency Plan" Sections 5.3 and 5.5 and the same EPIP listed above completely describes the make-up of LILCO's off-site organization. , Sixty copies of the revised Shoraham Emergency Plan dated May 1981 were submitted I to the Office 6f Nuclear Reactor Regulation of the Nuclear Regulatory Commission , I on May 27, 1981. This Plan was submitted in response to NURPEA737. LILCO's I emergency planning effort has closely followed the guidance of NUREG-0731 as well ' as NUREG-0654, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants". ] , J 1 I MY M.EEN$d4 tan 5MYid%Md5fs$k
*l SSER Item #7 Addenda As previously stated, LILCO connits to establishing an ISEG to be located at the Shoreham site. To assure additional independence of the ISEG from the operating pressures of cost and schedule and alleviate NRC Staff concerns, LILCO has reevaluated its previous position on reporting responsibility. The -
ISEC will now be assigned to the offsite organization reporting to the Manager, Nuclear Operations Support. The ISEG shall be composed of a multidisciplined group of experienced personnel, a majority of which shall not be recent college graduates. k d i
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a l T. O: . f RE: Independent Safety Engineering broup for Shoreham Nuclear Power Station s In May 1981, the NRC sent to the Federal Register a proposed amendment to the > Commission's Rules of Practice,10 CFR Part 50. This rule, which addresses the , same set of items contained in NUREG-0737, imposes new safety requirements for operating license applications. , The Commission has reviewed NUREG-0737 and has concluded that the positions I contained therein provide a basis for responding to the experience of the THI-2 ; accident. The Comsission has stated that ..." Applicants may, of course, propose , to satisfy the rule's requirements by a method other than that detailed in NUREG-0737, but in such cases must provide a basis for determining that the requirements of the rule have been met (1) " . [ The proposed rule states: "An onsite independent safety engineering group of l technically qualified personnel shall be provided to perform continuing systematic reviews of plant activities, including operating experience information that may .h indicate areas for improving plant safety. This group shall also provide recommendations and advice to an offsite high level corporate technical officer, ; not in the management chain for power production. (I.B.1.2)" At Shoreham, the responsibility for power production lays with the Chief Operating j H Engineer, with the Chief Technical Engineer providing on-line technical support 1 1 for operations and the Plant Mcnager. The Plant Manager has overall responsibility j u
,A for the safety of the plant, for adhering to the conditions of the 'bperating [u e
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a f (1) Attachment to letter of Mr- S. J. Chilk, Secretary of the Commission, dated u 0 - 5/12/81. i f tW ?%, r >,:..J.e?"l q TM q w i WQ,'Q w,4mnn- yyWWQff4.M.&.{n. wwwK'lm.:m3. v fw?;a,Lnym~C;a? n.. - c ? a .'w:T e calT. &.-u"F m:... m>qy.y:!
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a2-license", fc rotecting the health and safety of the public, and the environment, j i and to insure an efficient, safe, and teliable source of energy to the LILCO customer. It is proposed to have the Shoreham Shif t Technical Advisors the onsite indepen-dent safety engineering group (ISEG). These individuals will be on-shift on a rotating basis reviewing all aspects of plant operation. They will be qualified as Nuc1 car Engineers and will be able to directly monitor and evaluate all power maneuvers (Note: in BWR operations, the Nuclear Engineer monitors all power maneuvers and their effect on core parameters). Their knowledge of power maneuvers and core
- response makes them extremely aware
~
of the most trivial anomaly in the core and its performance. There will be some STA's who will be extra men due to the fact that it is planned for a surplus of STA's (six versus four for shif t coverage). These " free" STA's will perform continuous, systematic reviews of plant activities, including 1 operating experience information. It is not our position that this review be j f limited to the free shif ts only, but rather, that the review is on-going even during the shif t coverage; this keeps these individuals gainfully and produc- { l tively employed in monitoring the present safety status as well as look to improve saf,ety. Their priority status on shift however, is to provide technical
" accident assessment" and " operating experience assessment".
3 STA's report administratively to the Reactor Engineer and therefore to the Chi Technical Engineer's organization. This keeps them independent of power producwion. In addition, they will be included as a Subcommittee of the Review of Operations Committee (ROC) with their reports being submitted concurrently to ROC and the off-site Nuclear Review Board (NRB). -
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P It is LILCO's position' that it meets all the requirements of the rule, and at the ,
. I same time 'provides a good basis for its approach. j Utilizing the STA's in this way maximizes their involvement with plant safety, direct access to the plant management forum (ROC) and direct access to Corporate Officers (NRB). It makes use of the STA's talents, training, and experience to the fullest by having them always (day and night) performing the independent ,
review function. In addition, it gives them motivation and direction which we believe will minimize the turnover rate within the STA ranks. (The ACRS has voiced concern about the retention capability for degreed personnel, especially trained in operations engineering.)
- LILCO remains anxious to answer any additional questions you may have with regard to the ISEC. . .
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h i SSER f8 NUREG-0654 i i f LILCO is in general agreement and willing to commit to shift staffing as outlined in NUREG 0654 with the following differences. At LILCO the Technicians are multidisciplined in that HP and Rad-Chem Technicians are cross-trained to a great extent if not completely. Therefore, we would commit to one HP/ Rad-Chem Technician in lieu of the two different technicians. We do not commit to the mechanical and electrical maintenance personnel on normal shift. Personnel normally on shif t would generally be capable of performing any minor maintenance that night arise. Should the need escalate to need for mechanical / electrical maintenance support, they would be " called out". i We cannot commit to the NUREG 0654 thirty minute response (eg. call-out); however, we do commit to the sixty minute response with the exception of the mechanical and electrical maintenance personnel. The nature of the "rimergency" would need to be known as requiring these personnel. As a supplement to HP Technicians at the sixty minute point, we have trained our operations personnel in basic radiation protection. This includes familiarity with the use of survey instruments. In summary, a normal shift will comprise of ten personnel as follows: 1 Shift Supervisor 1 Shift Foreman 2 Control Room Operators 2 Auxiliary Operators - 1 shif t Technical Advisor 1 HP & Rad-Chem Technician J " Extra" Field Operators 10 At the sixty minute point we commit to the response of an additional twenty-one personnel which is the required ever.cy-six less the five mechanical / electrical maintenance personnel. D H s i i l O H l I ammEunk i % m m:2NTN%fLE*MWsM~R?.i'ib%]M'uinKMNWES4"4E 2%%MOMMSO
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, , f SSER NRC #9 LILCO is committed to implement a comprehensive training' program for all appropriate Corporate and Plant Staff Technical Personnel. -A description of the overall program including its n.anagement and implementation details will be prepared and forwarded for NRC review, 1
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I SSER #10 Maintenance Organization j LILCO Plant Staff will have 29 permanent personnel to do maintenance work not including the six management maintenance personnel. Of these twenty-nine,14 are " lead" mechanics, 8 are " apprentices", and 7 are utility workers. The top 22 are trained in accordance with the attached Station Procedure SP 31.001.01, '*Iraining and Qualification of Maintenance Personnel". Additionally, twenty MSD maintenance employees will be " certified" in accordance with above SP and will work at plant S 90% of their tire. A maintenance contract will be " bid" by the end of 1981 and will allow us to use craf t personnel as supplemental to LILCO maintenance personnel. This is for normal maintenance as well as outage maintenance. i< i 1 4
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i l lI L'Til hl . : '- ' ' ~ " .. SP Number 31.001.01
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b.{/[. .- . Revision 1 U$ ( / Date.Eff. 12/21/79 R
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TRAINI_NG AND QUALIFICATIONS OF MAINTENANCE PERSO NEL l ,. - I I I 1.0 ' PURPOSE - To provide a program 'for the training and requa .ification of Maintenance { Mechanics meeting the requirements of References 11.1 to ,11.4. . ;. - l . l 2.0 RESPONSIBILITY ~ 1 -- The Maintenance Engineer ,b P. b ; eEponsible for the proper implementation of this procedure. . - - I .
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3.0 d$SCCSSION 3.1 The Mechan'ic Training Program consists of three major sections: - h 3.1.1 Power Pignt Basic Training consisting of Plant Procedures, Policies and Document Introduction, Plant System Training and Skills i. I Training. -(Appendix's 12.1, 12.2, 12.3, 12.4, 12'.5 and 12.6)
<1 3.1.2 Advanced Mechanic Training consisting of Vendor Training and l Welding Courses for Al and B Mechanics, and Electric Production
. Training Center Courses.
- <1
. 3.1.3 Refresher Training which will include refresher training required
. by, Reference 11.1 and a program of continuing Maintenance and t Safety Training.
3.2 *Ihis program meets tb requirements of Reference 11.2 and 11.3. 3.3 Ind~vidual Mechanics may be exempted from spicific traintng requs.rements by the Maintenance Engineer based on prior training, experience, and present job requirements, except for General Training Requirements of Reference 11.1 . 3.4 This ' procedure applies to permanent plant staff Mechanics as defined in , Reference 11.1. 3.5 The following topics are contained in this procedure: [ Page i 8.1 General Requirements - 3 jhW . 8.2 On the Job Training During Preoperational Testing: 3
! 8.3 Power Plant Basic Training 3 <1 f 8.4 Advanced Mechanic Training 4 8.5 Refresher Training 4 ,', 8.6 Scheduling. . 4 8.7 Performance Evaluations -
5 Appendix 12.1 Plant Procedures, Policies and Document Introduction l<1 Appendix 12.2 Maintenance Training Schedule Appendix 12.3 Plant System Training <1 General Maintenance Training
- Appendix 12.4 Appendix 12.5 Advanced Maintenance Training ',
Appendix 12.6 Electrical Maintenance Training . Appendix 12.7 A-1 Mechanic Advanced Vendor Training Appendix 12.8 B Mechanic and Utilityworker Advanced Training Appendix 12.9 A-1 Mechanic Evaluations I Appendix 12.10' Mechanic Training Evaluation 4.0 PRECAUTIONS _ =_ N/A ,
'SP 31.901.01 Rev. 1 12/21/79 Page 2 D em DM, v," '
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- 5'. 0 TREFEQUISITES ,
g f Personnel assigned to the Plant Staff as Hechanics shall have completed an employee selection program. b) 6!0 LIMITATIONS AND ACTIONS t y 6.1 Initial plant staff Mechanics should complete general employee training
; requirements prior to initial fuel load in accordance with Reference 11.1. ,t
{7.0 TEST EQUIPMENT t
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(
. 8.0 PROCEDURE
[ 8.1 .Ge.eral Recuirements I - i 8.1.1 Mechanic training shall be evaluated for effectiveness by written { examinations, oral examinations, and/or practical demonstrations by '
- the student, where applicable.
I {, 8.1.2 Training evaluations should be. documented on SPF 31.551.91-1 and ~ i filed in accordance with Reference 11.4. e .
! 8.1.3 Croup records of lecture attendance are satisfactory. ? -
- 8.1.4 Mechanic training'should be performed in accordance with lesson plans which should be filed by the Training Coordinator.
){ 0. -.8.2 5
On the Job Training During Preoverational Testing
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' Mechanics should participate in repair / rework and testing during the
{ preoperational phase of power plant construction wherever practicable. i- . j 8.3 Power Plant Basic Training . _ _ _ _ _ _ _ _ _< 1
; 8.3.1 Mechanics of all Crades and specialties should participate in
- i. Mechanic On Site Training except as noted in the course outlines. s I NOTE: Power Plant Basic Training is broken down into Plant ,.
Procedures, Policies and Documents Introduction, Plant j Systems Training and Maintenance Skills Training. { f
.8.3.2 Plant Procedures, Policies and Document Introduction should consist ]
l of the following courses: ! [ 8.3.2.1 General Employee Training Program, conducted in accordance with Reference 11.1. 8.3.2.2 Ceneral Indoctrination Training listed'in Appendix 12.1. S.3.3 Plant Systems Training should consist of the courses listed in < .1 SP 31.991.91 Rev. I 12/21/79 Page 3 (
- - =
.}
- b- "' '*"' ' -'
ls
, Appendix 12.3. $.
8.3.4 Maintenance Skills Training is broken down into the three following
~
i major courses in which mechanics of all specialties should < lj O ,
. participate: i
)
8.3.4.1 Ceneral Maintenance Training (Appendix 12.4) 8.3.4.2 Advanced Maintenance Training (Appendix 12.5) t l 8.3.4.3 Electrical Maintenance Training (Appendix 12.6) 8.3.5 Part or all of the Maintenance Skills Training requirements for "B" Mechanics and Utilityworkers may be fulfilled through satisfactory completion of the appropriate training courses conducted at the Electric Production Training Center. 8.3.5.1 "B" Mechanics and Utilityworkers should pa$ ticipate in the courses in Appendix 12.8 every 6 months, as defined by the Electric Production Training Center. NOTE: Personnel failing to comply .with this outline shall be ineligible for further advancement as Mechanics until successful compliance can be shown. 8.4 Advanced Mechanic Training - 8.4.1 At the completion of Power Plant Basic Training, A-1 Mechanics
,Gg should attend vendor and specialty courses as indicated in Appendix .O' -
12.7. 8.5 Refresher Training ~ ~ - 8.5.1 Mechanics should participate in at least two hours of refresher training per month starting approximately 6 months after fuel loading. , 8.5.2 Refresher Training may consist of, but not be limited to:'- 8.5.2.1 The annual requirements of Reference 11.1 8.5.2.2 .'. A review of Maintenance Training Courses 8.5.2.3 Rehearsals and Discussions of upcoming maintenance 8.5.2.4 Reviews and discussions of completed maintenance 8.'6 , , . scheduling - " 8.6.1 Maintenance Training for the initial group of Mechanics should be scheduled in accordance with Appendix 12.2. ~
~
- +
SP 31.9@l.gl Rev. I 12/21/79 peg 4 f
. . _ _ .__ _. . _...a. -
_<__.7..__-_..2__... , NOTE: Maintsntnes Training for raplectmant personnal should b2 scheduled as in. Appendix 12.2 starting as scen es practic,able after the personnel arrive on site. 8.7 Performance Evaluations i i O' . 8.7.1 Mechanics shall be evaluated just prior to the completion of their l first 6 months of training. Mechanics failing to successfully complete the performance evaluation shall be considered i ! unsatisractory for assignment as a Mechanic at Shoreham. 8.7.2 A-1 Mechanics should be evaluated in their specialties in PI accordance with Appendix 12.9. . 9.0 ACCEPTANCE CRITERIA N/A t 10.0 FINAL CONDITIONS i 10.1 Training evaluations submitted to Plant Administrative Coordinator for : filing in accordance with Reference 11.4.
11.0 REFERENCES
. 9 11.1 SP 12 914.93, General Employee Training Program -
~
11.2 Reg. Guide 1.8-1971 lersonnel Selection and Training'
)'
11.3 ANSI N18.1-1971, Selection and Training of Nuclear Power Plant Personnel J. Os S-tions 4.s.3. 5.1. 3.3.4. 5.s and 5.6 m
--11.4 SP 12.914.02 Training and Qualification Folder .. .
m
,_12.0, APPENDICES 12.1 Plant Procedures, Policies and Document Introduction <1 l u
12.'2 Maintenance Training Schedule . - Power
~
12.3 Plant Systems Training
- Plant y
12.4 General Maintenance Training Basic
'12.5 Advanced Maintenance Training Training H 12.6 Electrical" Maintenance Training
. g 12.7 A-1 Mechanic Advanced Training W
- 1 12.8 B Mechanic Advanced Training -
h 12.9 A-1 Mechani: Evaluations ' q l 12.10 SPF 31.001.91-1 Mechanic Training Evaluation ' @* O .
. . . . . 1
' SP 31.961.91 Rev. 1 Page 5 112/21/79
# ' 'V' ? %M NM _~ hT_> g 4 m _. _ . _
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ti
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, Appendix 12.1 f"T .
Q
. PLANT PROCEDURES, POLICIES AND DOCUMENTS INTRODUCTION I 1 LESSON TITLE ,
' _MTALP* <1 a
C:ntrol of Loaned Tools and Equipment' ,
.808 Equipment Clearances }
.810 Fira Prevention Watches, Patrols and Permits
.811 Maintcnance Philosophy
.812 Maintsnance Procedures
. .814 Maintanance Work Request Form
. 816 Pr v:ntive Maintenance Program "
~
.818 %
Site Organization '
.820 Spsre Parts Program
.B22 -
Survaillance Program q LjerDocuments
' v . = .824 I a
.830 Qunlity Control Procedures- - -- ~~
-- ~~
.832
. .[
Org:nization and Administration of Fire Protection Program .834 2 Fira Brigade Organization, Response and Drills
.836 Sscurity Orientation '
.838 Statica Health Physics Policy cuides and Controls
, f.840
%3tamination Contr.o1
.842 Isapirator Program
.844
;cdiction Work Permits "
, . .846 ' '
!ca cf Solvents .
Mechenic Training Administrative Lesson Plan "
.848 i i
. ,4
- k. . l W -
g. SP 31.901.91 Rev. 1 12/21/79 Page 6
.. i' r . .
.i u - .- - - -~ ~" x = ~ ~ ~ ~~
- - - m-_ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ , . _ , , _
100., ,
. i 6 e e ~**
75- - E
,< e g General UTILITY h N.
Maintenance j
- g. ,.
50 .-4 oa a Trai,ning i o O wo hM ? NDC t/3 C t <:< oe w . aae aC c -4 ' Coa 25 eoo ADVANCED MAINTENANCE TRAINING s-4 S.4 C .e
-e a u
- p. m c .me ;
e 100. -
)
m 4 75 f d- General g '- _ g. y- Maintenance 50 - doa ou6 a xe Trainin8 -
-,\ -
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.g g ADVANCED MAINTENANCE TRAINING 25 8 A-1 Mee o
.5
- p. p8. A p. s
~
D - M100 ,. - -
' ~
.N ...
g - s . g Mi .h M 75 ;q y ;a g General j g . ' ~.~
~ ~ ' ~ ~
jg, ~g Maintenance 0; 50 f. y t oc c
&2 ~4 Training h
MC E & C .
- 1 25 - @g5 gT ADVANCED MAINTENANCE TRAINING d
e .-e
- p. pu.
e .au a A p. H . ,
.m.
g100 , - 1 o j$ 75 . . [l General (j w 0.e g
** 50 ' M T' _u ' ~ **"****
y*f R, Training
- p. = c .
.o . = .c. .
tag y5 . ADVANCED MAH;TENANCE TRAINING 25 . _ y[lg
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- o. s - - -
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...___,_.=.. , _ _ . . - - -
- p. pu. C - '
_31 100 , ._--[ \ m ASME 'i 75 ~
.* l ,' "*"**** "E'"ING mg 5 Maintenance S. y ,
- 50 yg" R. Training- .& p
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. QUALIFICATIONS d.-
U G G UC
- 25 Coo C we -
- ed O o C 4 ,.
.4 s.s o u . !j
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--- --.-4. s ._- . _ _ . _ _ -
. . 1 12 10 9 -
8 7 .
~
6 5--~~ j
. .- . ,t;
- ~ * ~ ~ ~ - -
MONTHS PRIOR TO WEL LOAD 4 l Q - ,. +' > ~ ~n.- x- , ,, , _f
_ ; :_. . . _ _,i _ _ , ]_~] ~
. . _ . . .a . .,
.. ,i .
.43 .,.
s . 1
'. APPENDIX 12.2 .
HECHANIC SCHEDULE 'I .
!s 1' e, r n .
+
t
. r yl .
(. 1 , 1 W 3 SCHEDULE r e- .
- u .
(- Advanced Vendor Trainier k j . t i' . . 1
' P . SCHEDULE l :i t
i .- . . 1
- f. -
1 achanic Adveaced Vendor Training ~ t .._ _ . . l senEDULE l. . d b i 1 1 Y
-2 ,
[Ee5m_nic Advane'ed Vendor Training ~ ; ~,
~.,
{ WELDER SCHEDULE
._i,
! ;G n
. y
- . tfja IF g
- --- , -- 5 A l'HeclianEI5anced Vendor Training .
~
f: n 3 2 1 Fu.el .- ' I
- 4 .. Load .
; 'SP 31.001'.01 Rev. 1 II
. j 12/21/79 Page 7 he ~ me -w.w,.r . rwax ~~myy,- .. . ,,- .
_w-: _
--.-...u . - . - .-u-..x~.m.~.----=-- %: "~ ~
l ll
. Appendix 12.3 l
Page 1 of 5 i:
' <1
- PLANT SYSTEMS TRAINING l
Nucler Steam Supply Systems MTSLP R2ceter Vessel and Internals .705 l Crntrol Rod Drive Assembly . .005 C ntrol Rod Drive Hydraulic Control Unit .004 Raceter Core Isolation' Cooling
.119 Raceter Recirculation .120 R2aidual Heat Removal .121~
Source Range Monitoring *
.601 Intermediate Range Monitoring -
.' . .602 -
Locci Power Range monitoring .603 Trcvsrsing Incore Probe . .605 : Ra ctor Vessel Head Flange Leakage Detection .625 u_, Rafu21ing Platform '
.703 Fu21 Handling and Incore Tools Operation -
.704 I C ntrol Rod Drive .106-Enlence of Plant - 1 ,
Aux. Boiler and Aux. Boiler Steam Fuel Oil Supply , , . .101 Circulating Water and Vacuum Priming , .102.1 ~ Screenwash and Traveling Screens .102.2 Cond2nsate - -
. .103 -
Der.inatalized water'- Make Up Storage and Transfer *
.107 Fasdwater System , .109 I Extrection Steam .110.1 I e
{ 9 4 s SP 31.9W1.91 Rev. I 1 12/21/79 Page 8
]
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. t- .
, . . Appendix 12.3 Page 2 of 5 Balnnee of Plant-1(Continued) , MTSLP <1 in Steam Moisture Separator Reheater .110.2 Fxdvater Heaters *
.110.2 f H20 tar Drains .110.4 Main and Auxiliary Steam -
.116 L
Pltnt Air .
.117 I;
- RBCLCW .118 TBCLCW .126 Circulating Water Inlet and Discharge . .135 Balence of Plant-2 Turbine Steam Valves . .006 Cen2rator H2 and CO2 Cas ,
.111 i! C2narator H2 Seal Oil .112 -
i ;srator Stator Cooling t c .113 - f Steam Sealing ,
.124 /
' Turbine Generator~
.127' <
Turbine 1:.xhaust Hood Spray
.128 f Turbine High Pressure Control Fluid (EHC) , .129
. L:
Turbine Lube Oil and Turning Gear- * -
.130 ,
WJll Water and Domestic Water , . .131
~ ?
Hyp chlorination System
.132 Luba Oil Conditioning System '
.134 L
. 1 C:rb:n Dioxide '
.501 Deluge and Sprinkler j
[' .
.502 -
t s' . f SP 31.991.91 Rev. 1 12/21/79 Page 9 ) 3
. n m
h
w., ~ ..
, s Appendix 12.3 Page 3 of 5 R v21rnee of Plant-2(Continued) MTSLP <1 N
Fira Main Distribution
.503
'Stction Cranes, Hoists and Elevators 850 E1cetrical Canarator, Excitor and Voltage Control .115 138 KV fystem and NSS Transformer *
.301 69 KV System and RSS Transformer .302 H2in Generator Transformers .303 4160V Normal Bus Distribution .308 4160 V Emergency Bus Distribution , .309 480 V Normal Bus Distribution '
.310 480 V Emergency Bus Distribution -
. .311' 120 VAC Reactor Protection System MC Sets .312 VAC Uninterruptable Power Supply (UPS) .313 120 VAC Instrument Power , .314 -
125 VDC Power Distribution .315, 24 VDC Power Distribution .316 AC-DC Lighting Systems ,
~.317 Plcnt Communications .319
~
Plcnt Cathodic Protection \
~.321
_Hantine,VentilatdngandAirConditioning MTSLP .. . H3t Water Heating and Glyc'o1 Heating .422 HVAC Ventilation Oriented .430 HVAC - Chill Water Systems *
.431 Cenaral HVAC Systems -
.432 L
o .- h
~
SP 31.001.01 Rev. I 12/21/79 Page 10 e
, , . , n,w w .a w n w m .n ~ ~ -~ ' "'
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,i- -
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. j Appendix 12.3 f
~
. . Page 4 of 5
, &ty Systems MTSLP <1
- Supprsssion Pool, Cooling and Cleanup .001 f Drywell Drains - Equipment and Floor .002 i
3Loss of Coolant Accident (LOCA) .008 b i . IDiosal F.O. Storage and Transfer .108 ;
; e
! ctr dby Liquid Control .123 .
{ Int'igratedE.C.C.S .200. - I
; Auto Depressurization System .
.201
; High Pressure Coolant Injection .202 C,cra Spray ,
.203 f Low Pressure Coolant Injection *
.204 ,
i IEmergency Diesel Ceneratore . .307 t I Primary Conteinment Leakage Detection ,
.403 '
la 1 M7v211 and Suppression Pool
~ .654
- T jRADUASTE
[.CtudtasateFilterDemineralizer .
.104 --
3 3 . . (: f Cindinser Off-Gas Removal (SJAE) .701 t
) Equipment Drainage and Floor Drains - '
.702 , ,
t - t a Fu21 Pool Cooling .707 g Fusi Pool Cleanup , ,
.708 i
I Recctor' Water Cleanup .709 ?
? .
[LowConductivityLi.quidFadwaste . .710'
' Flear Drain Filter. *
.711.1
~ High Conductivity Radwaste ,
.711.2 t
; R2ts:nt Chemical Liquid Radwaste , .712 ,
j . L - l,
~
SP 31.001.91 Rev. 1 g- . 12/21/79 Page 11 L e - f 2 aam m n awaaumnmawsmamamum
. . __ :., . a_', g ;m ; _;, .
1-Appendix'12.3 Page 5 of 5 ,duts te(Continued)
~
!!TSIP <1 9 *
.713 nid Redwast-tsscus Radwasa.4 (lloidup) ,
.714 iquid Radwaste Recovery System '.716 iquid Radwaste Discharge System .717 -
iquid Radwaste Spent Resin System .718 Huid Radwaste Evaporator Botton System .719
, e 1.
B.. -
.c._
r.
.- f.
's
. s t
. .i i
SP 31.961.91 Rev. 1 ' 4 i 12/21/79 Page 12 y
. . i 4,
' , y s .- ,,' , . , , . ,
-, . ~ _ _ . . _ , . _ . _ . _ ., . . _ _ _ _ - - .. - ___ _ _.
j ,,, ~_
. 1
- 3
! ,- . . f CENERAL MAINTENANCE TRAINING . [
e '
<1 f h QThe courses for General Maintenance Trtining, Advanced Maintenal ,
4 NUS and Technical Publishing , Corporation (TPC). The NUS material Theconsists TPC units of aconsist ' 1- videctaped presentation, .v.-itten material, and shop exercises. J cf printed material to be administered by an instructor to the student. ' 1 .
- MECHANICS VENDOR ATTENDING COURSE TPC All Basic Shop Math All
' TPC Elements of Mechanics TPC
- All Machine Shop Practices All .
NUS Personal iafety All-NUS Basic Hat Tool NUS All
)
Crinding Tools and Shop Hardware All NUS I Heasurement Tools NUS All Caskets, Packing, Seals All fs Hazardous Substances NUS All j Non-Destructive Testing Basic Bearings NUS NUS All NUS All Rolling Surface Bearings
- fr
- Basic Lubrication NUS All All NUS' A Pipe and Pipe Fittings All f Intro. to Electricity and Electronics TPC All ,
Basic Rigging , NUS , l .
~
W d . O g a a e 4 6 1 e L g SP 31.991.61 Rev.1 -
- 12/21/79 Page 13 r._
. g m.m..+.w .
4.sww:menwwgggpx5%%w an t _ m m - ~ ~ e. m w n w w ,n u- - n . ~ , , ww n.nc m., w,-
~ - ~ - -
t-e = l Appendix 12.5
. . < li-
. ADVANCED MAINTENANCE TRAINING g 30TE: See Appendix 12.4 for description of vendor training material.
MECHANICS Course Vendor Attendg Valve Maintenance I i NUS M. R, W. B V21ve Maintenance II NUS M. R, W. B C;ntrifugal Pumps I NUS M, R, B Centrifugal Pumps II NUS M, R, B P2sitive Disp. Pumps I NUS M. R, B r P:sitive Disp. Pumps II NUS M, R, B Cauge Class Maintenance NUS M R, B Steam Piping Au:ciliaries I NUS - M, R, B, W ' Steam Piping Auxiliaries II NUS .M R, B W ; Basic Hydraulics TPC M, R, B ' Hydraulic Troubles'nooting ~ TPC . . . M, R, B Intro. to Arc Welding NUS W. B Intro to Cas Welding NUS W. B Thermal Insulation NUS M. R, B
. Safety Valve Maint. I NUS . M, R, B Safety Valve Maint. II NUS -
M. R, B Advanced Rigging I NUS M.R,B . Advanced Rigging II NUS ::M, R. B OBssicPneumatics TPC M, R, B Pneumatic Troubleshooting TPC M, R, B " Troubleshooting Refrigeration Systems TPC ' - M, R, B - - Troubleshooting A/C Systems TPC M, R, B Ensic Diesel Engine Maintenance NA M. R B Advanced Diesel Engine Maintenance NA M. R, B L
. . r:
~
.; i e* _
, . t
- f
;9
- I SP 31.091.91 Rev. I 12/21/79 Page 14 b
L
1 a v. - ~: ? . a u . . . z .. - - _..._.m.,_ __-.,.... ._.___ __2 ~ .t.L. m a a A - . u_ , _ . .w.m. - l Appendix 12.6 ,
<1 <
}. .
ELECTRICAL MAINTENANCE TRAINING l O See Appendix '12.4 for description of vendor training material. ,
. MECHANICS COURSE _ _ _
VENDOR ATTENDING Batteries and D.C. Circuits TPC E Trinaformers and A.C. Circuits TPC E . Elsetrical Measuring Instruments TPC E i Electrical Protective Devices TPC E
+ D.C. Equipment and Controls TPC E ' Single Phase Motors TPC E Three Phase Systems TPC E ,
A.C. Control Equipment TPC E , Electrical Troubleshooting TPC. E R Os .
>=
- ~
. .. \.
[ l
. . . . (
1
. i t
t. 4 0 . SP 31.951.$1 Rev. 1 l 12/21/79 Page 15 . I I >
~
- -- -- - __. . .. , __ . . m . ,. _ . _
, _ _ y.7 + -- _: . . _ _ _ :.- . i ..~.a au w .- -w-m= a . a. .2:
7 , i . .
- Appendix 12.7
} - *
;A
'O ,
A-1 MECHANIC ADVANCED VENDOR TRAINING , W H;chtnic Advanced Training consists cf selected vendor training course's to be attended , Iby A-1 Mechanics within their specialties. , 1
< ~
i k RECOMMENDED MECHANICS iCOURSE TIME REQUIRED ATTENDING
- f.1, DeLaval Diesel Maintenance 5 days 2R, 2M, 2E, 2W i
! 2. 2MK Model EDR Milling Machine '3 days 2M L
? 3 '. 24"/52" Sliding Bed Cap Lathe and Y[
i Radial Arm Drill Press Operation 1 day 2M .
~4. BWR Maintenance Training 7 days. -2R, '2M, 2E, 2W i 5. Non-Destructive Testing 5 days 2R, 2M, 2E, '2W i
k 6.' Switchgear Maintenance 3dEys 2R, 2E [ t.
) 7. Limitorque Maintenance 1 day 2,R, 2E, 2M ..
i O Welder traininE - lo weexa 2W 1. , i 9. National Electronic Coil Seminar 4 days 2E
- 4. ~
p 10. Vibration Measurement - - - 4 1/2 days-- 2E, 2M
~ -
t i 11. Turbine Building Crane Operation 'and Maintenance 3 days 2R, 2M, 2E, 2W
~
f ' t ' j 12. Fuel Handling 10 days 2R, 2M, 2E, 2W , f 13. Reactor Bldg. Polar Crane Operation $- 1 and Maintenance 3 days 2R, 2M, 2E e _ i j 14. C.E. B-J Recire. Pu::sp Seals 3 days 2R, 2M <1 i .
! 15. Target Rock Relief Valve Maintenance 3 days 2R, 2M,
' 16 CRD Maintenance 3 days ,
2R, 2M, 2E . CE = Electrician, M = Machinist, R = Rigger, W = Welder, B = B Mechanic ? . n U
?
1 I SP 31.001.01 Rev. 1 __ flf2AS1Rf5X1 Grcn RS _. _ d
Appendix 12.8 i B MECHANIC AND UTILITYWORKER ADVANCED TRAINING
\O -
l . . t 3 Mechanics and Utilityworkers should phrticipate in at least one of the below listed crurses every six months until all courses are satisfactorily completed, in accordance with the requirements of the Electric Production Training Center. s 1. General Nechanics Course <1
- 2. Basic Welding Course
- 3. Basic Machine Tool Operatica u
- 4. Basic' Electricity Course s 1
- 5. Basic M111 wright Course 'I 1
1 1 1 1 1 l 0+' e .
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- 6
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y i SP 31.901.91 Rev. 1 , .
. 12/21/79 Page 17 .
A. hg . . ,d 7%' N' * *
-- - . . . . . . . . - . ..- - - . - --. .- -. --- ~ - - -.-
j
~
Appendix 12.9
.q . Page 1 of 4 l L) -
. A-1 MECHANIC EVALUATIONS Prict to the completion of his last 6 months of training, each A-1 Mechanic shall be cvaluated for satisfactory performance in his specialty using the following as a guide:
Electricians -
- 1. Overhaul of a pump motor, including removal from service, holdoff procedures, disassembly, repair and reassembly. <1
- 2. Perform insulation resistance checks on a piece of equipment, including motor, leads, switchgear and busswork. Mechanic should show capability in interpreting megger and ductor readings. .
- 3. Determine the electrieni operational sequence of a piece of equipment from electrical diagrams and prints. .
- 4. Successfully troubleshoot problems in both' h'igh and low voltage circuit breakers and swite.. gear.
~
- 5. Written test on basic electrical fundamentals such as Ohm's Law, Kirchoff's Laws,
{ circuit calculations, magnetism, power, ef fects of induction, capacitance and
!p impedance. 4 id- .
Mrchinist , A. Written Test _. -. .
, The candidate should be able to show his knowledge in the following:
i .
- p. 1. Mathematics ,,
- a. Tapers r - .
; b. Angles -
,, j r-
- c. Diameters '
- 2. Lathe and Hilling Machine Construction
- a. Parts -
.. l l
'. b. Purpose ,
- 3. Cutting Tools and Cutting Speeds for various metals. ,
~ ~
- a. Sketch 3 view drawings ,
~
L b. Interpret plans and drawings t
- c. Use of precision tools and instruments .
e. l l c5 "I t r' rf t di e m. 1
,,,_=,,__....w..
.=..n=.. . - - - . __, . . , . . - . _ , - - - -.. _. -. n, ,_
7 . . . . - - - . . * * - - - * * ---- f
. t Appendix 12.9 .
O Mrchinist (Cont'd)
. Page 2 of 4 i
I A. (Cont'd.) ' 1
- 5. . Threads and Gears
- a. Diameters .
L
- b. Pitch !
- c. Fit
- 6. General Plant Maintenance '
- a. Repair
- b. Evaluation cause of problems ,
1
- c. Alignment of pump-motor * '
Tasting: Practical
~
l . Tha ccndidate should be able to demonstrate his ability in the safe and efficient use ( o chine shop equipment, (1.athe and Hilling Machine),.in the following areas: I
- 1. Read and interpret compliceted plans and drawings a.- , ability to duplicate a part from a 3 view drawing including adherence to c1cse tolerances ,
- 2. Set up of material and parts in machines
- a. Centering (4 jaw check)
- b. Use of dial indicators .
- 3. Selection and Crinding of Cutting Tools '
4 Nachining (Lathe & Hilling Machine) ,
- a. a Use of micrometers and calipers (vernier) "
- b. Nachine feeds and speeds -
- c. Tolerances
- d. Finishes ~
g
- e. Cleanup .
SP 31.901.01 Rev. 1 3 12/21/79 Page 19 g *' M *I - ink Ir ' _ = - -- *# '
, 4 Tb ' b - N #
J . s - o . Appendix 12.9
' Page 3 of 4 ! ;- ( )
ai,,=,
- 1. Written test on the types of rigging ~ equipment and the work limits of each.
- 2. Demonstrate the abilty to select the equipment and rigging required for the removal and replacement of a large unit, such as a circulating water pump, and determine the proper procedures necessary to complete the job.
- 3. Demonstrate a knowledge in the proper arrangement of hitches, knots and slings; OSKA approved hand signals and both OSHA and LILCO safety regulations pertaining to rigging and scaffolding.
f
- 4. Demonstrate the ability to properly align a pump and motor according to procedure, recording the proper readings and information for maintenance history.
records. , Welder A. Written Test . All candidates should be required to show that they have knowledge in the following areas: .
- 1. Mathematics - .
( .
- a. Angles * -
L
~
- b. Diametera - .
- c. Ohms Law .
- 2. Piping
~
- a. Bends, offsocs *
- b. Radius, wall thickness, nominal pipe size
- 3. Welding Material
s
- a. Base metal !
- b. Filler met,als .
~
- c. Electrode nomenclature *
.s G SP 31.001.91 Rev. 1 i 12/21/79 Page 20 i
' - .. e n. 9 '
,o * *
.r. .- .
, m . a . .
s' = Appendix 12.9 m Page 4 of 4 () - 1641dar (Cont'd.) A ., Written Tes't (Cont'd.) . I-
- 4. Safety ,
- s. Oxygen and MPP Rer;uirements (pressures, safe working distances)
- b. Torch Handling ,
. c. Safety apparel .
B. Practica1' Tes t . This testing should concentrate in the use of Gas Tungsten Arc welding (GTAW) equipment on the welding of carbon steel pipe with a filler metal of less than 6% alloy and the welding of stainless steel pipe using an F-5 filler metal (chrome-nickel). The test specimens should be welding in the 2G position (vertical) and the SG position (horizontal) 'or the 6G position (45' angle) may be utilized as an alternate to the 2G and 5G r esitions. ,
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e e W-O R . . o - Appendix 12.19 . [] v . MECHANIC TRAINING EVAI.UATION Trainee . - Evaluator / Grader - Date t Subj:ct . - Typ2 of Evaluation Written Exam . . Oral Exam (questions attached) , 1 Performance Evaluation
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Unsatisfactory , Written Exam Grade . _ _ _ _r A crpy of the written exam, or the performance evaluation requirements are filed in ccesrdance with SP. 12.914.92.
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12/21/79 Page 22
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t SSER NRC #11 The development and implementation of NRB has been evaluated by a consultant to LILCO. The resulting report was reviewed by LILCO and returned for reevaluation by the consultant. The reevaluation was necessitated by the recent corporate reorganization and the on-going intervenor negotiations. The consultant report will be resubmitted for LILCO review. The resulting impice ntation L:tions will be submitted for NRC review. s
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SSER 6/4/81 (Management Review Summary Status Follow-up Item Responses NRC Item 12 1 Amend ROC Committee FSAR writeup to reflect current Standard Technical Specifica- $ tions (Section 6). LILCO Response The ROC Committee FSAR writeup will be amended to reflect Standard Technical Specifications, Section 6, when Shoreham's Technical Specifications are finalized and approved. This will be consistent with Regulatory Guide 1.33 and ANSI 18.7, 1972. i NRC Item 14 1. l The Operating Engineer must have at least 4 years power plant plus 3 years nuclear plant experience. No credit can be given for training and education (ANSI 18.1 h 197L) . There are no NRC standards for the position of Operating Engineer; there- " fore he must meet the same qualifications for the position of Chief Operating Engineer. (FSAR 513.1.3.1.6) t LILCC Response FSAR Section 13.1.3.1.6, " Operating Engineer" will be amended to include the 4 minimum experience requirements identified in FSAR Section 13.1.3.1.6, " Chief ' Operating Engineer". NRC Item 16 Operators, including NASO, must have 1 year of power plant experience, not 6 months as stated in FSAR 513.1.3.1.19. Must meet the same requirements as an RO. Amend FSAR. LILCO Response FSAR Section 13.1.3.1.19, " Nuclear Assistant Station Operator (NASO)", will be amended to require 1 year of nuclear power plant experience. This experience re- , quirement is as defined in ANS 3.1 Draf t Addition 12/6/79. a b P J YhYHD.'LY l' Yi . ' L b ?' ? ' Y ~ ' ' ' ^}}