ML19225B287

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Progress Rept on Program to Review Fort St Vrain Inservice Insp & Testing
ML19225B287
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 06/05/1979
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19225B285 List:
References
PP-790605, NUDOCS 7907240456
Download: ML19225B287 (44)


Text

{{#Wiki_filter:.. T PROGRESS REPORT ON THE A \\ O PROGRN4 TO REVIEW C Q FORT ST. VRAIN g bh O INSERVICE INSPECTION AND TESTING c. 91P m N V 4

.-e u INSERVICE INSPECTION AND TESTING PROGRAMS 0 AN ISI REVIEW PROGRAM HAS BEEN ESTABLISHED TO REVIEW FORT ST. VRAIM SURVEILLANCE REQUIREMENTS. O THIS REVIEW EFFORT IS EXPECTED TO RESULT IN NEW RULES - A REVISED llLSERVICE INSPECTION AND TESTING PROGRAM FOR FORT ST. VRAIN. O THE NEW RULES, IN TURN, WILL REQUIRE AN ISI IMPLEMENTATION PROGRAM TO BE ESTABLISHED TO PUT THE NEW RULES INTO EFFECT. M' m N

.~ i ISI REVIEW PROGRAM B ACKGROUND/111 STORY - THE JANUARY 1972 AEC SAFETY EVALUATION REPORT CONCLUDED THAT THE PROVISIONS CONTAINED IN THE FORT ST. VRAIN TECHNICAL SPECIFICATIONS (SURVEILLANCE REQUIRE-MENTS) FOR AN INSERVICE INSPECTION PROGRAM WERE ACCEPTABLE. HOWEVER, THE COMMIS-SION, (AEC/NRC) REQUIRED THAT THE INSERVICE INSPECTION PROGRAM BE REVIEWED AFTER FIVE YEARS OF REACTOR OPERATION AND THAT PSC PROPOSE NECESSARY MODIFICA-TIONS BASED ON THIS OPERATING EXPERIENCE. - THE FEBRUARY AND JUNE 1976 AMENDMENTS TO PART 10 0F THE CODE OF FEDERAL REGULATIONS, SECTION 50.55A, CHANGED THE REQUIREMENTS FOR INSERVICE INSPEC-TION OF LIGHT WATER COOLED REACTORS BY INVOKING THE RULES COUTAINED IN THE ASME BOILER AND PRESSURE VESSEL CODE, SECTION XI, DIVISION I. - AT THIS TIME, THE INSERVICE INSPECTION REQUIREMENTS DELINEATED IN 10 CFR 50.55A ARE NOT DIRECTLY APPLICABLE TO FORT ST. VRAIN. - ASME RULES FOR INSERVICE INSPECTION OF GAS COOLED REACTORS HAVE BEEN UNDER DEVELOPMENT SINCE 1975 (SECTION XI, DIVISION II)J THE LATEST PROPOSED RULES WERE ISSUED FOR INDUSTRY REVIEW AND C0liMENT IN SEPTEMBER OF 1977. THE STATUS tx (( OF THE DIVISION !! RULES IS UNCERTAIN AT THIS TIME. .ex

- TWO PSC REVIEWS OF THE EXISTING SURVEILLANCE REQUIREMENTS HAVE BEEN PER-FORMED SINCE THE START OF FSV REACTOR OPERATIONS IN 1974. THESE PSC REVIEWS, IN THE SPRING OF 1976 AND THE SUMMER OF 1978, FOCUSED ON THE IMPACT OF IMPLE-MENTING A PROGRAM AT FORT ST. VRAIN BASED ON THE ASME RULES AS WELL AS ASSESSING l THE FIRST FIVE YEARS OF REACTOR OPERATING EXPERIENCE. - PSC INFORMED THE COMMISSION IN OCTOBER 1978 0F THE RESULTS OF THESE REVIEWS AND THE APPROACH BEING USED TO COMPLETE THE ISI REVIEW PROGRAM. TWO CONCLUSIONS WERE REPORTED AT THAT TIME, NAMELY: - REACTOR OPERATION THROUGH 1978 DID NOT OFFER SUFFICIENT BASIS FOR MODIFYING THE CURRENT INSERVICE INSPECTION PROGRAM. - APPLICATION OF THE ASME TYPE OF RULES FOR INSERVICE INSPECTION WOULD NOT PROVIDE EARLIER OR BETTER INFORMATION CONCERNING THE LEVEL OF PLANT SAFETY BEING MAINTAINED OR DETERIORATION OF SAFETY RELATED FACTORS THAN THE CURRENT PROGRAM, BUT COULD ENTAIL CONSIDERABLY INCREASED INSPECTION COSTS AND ty Ch REDUCED AVAILABILITY. N m

~ ND - IN JANUARY 1979, THE COMMISSION AGREED THAT COMPLETION OF THE REVIEW DEVELOPMENT OF ISI PROGRAM REVISIONS COULD BE EXTENDED FOR AT LEAST ONE Y.'R. SPECIFIC ASPECTS OF THE EXISTING INSPECTION PROGRAM WERE OUTLINED, 9 HOWEVER; EARLIER REVIEW. - IN MARCH 1979, PSC RESPONDED TO THE INQUIRIES FOR WHICH THE COMMISSION REQUESTED EARLY REVIEW. THE PSC APPROACH BEING USED TO DEVELOP A MODIFIED INSERVICE INSPECTION AND TESTING PROGRAM WAS DESCRIBED TO THE COMMISSION AND A COMMITMENT MADE TO REVIEW THE RESULTING PROPOSALS BY THE END OF JULY u m N r N C. yd

Y R T E E R '- L N F I N A E S S U D E A S N D L V L M I N U R A T Y I O U C A N T E H S I E I N N R L R S E W S G H I E I H E N T N C H B I S I E S N A W I, L V A E T T T I S E R T S N I I N E E A A R V E R X I M H V O E A E T A R E A H T R L S S E V E D R T Y N N H N O M A T O T F F I I O A R I T E Y T R O T S S T E T N T V F C E S L I E H E C T Y O L R P N R S R I D G I I T O S A O B L S F N H F D Y A I C N T I OT N T M N E A E L I R A H E H F E S O R C T S A R I D F G U D T S E O S N N N T M M T T R A I E R A C A P F N I S A R E O , D O E' L G R E G M E P H R P O I C N E O N M T W R D N I S R I O L T P E T O F A C O C I S P T T R E E W B R E R D N S E F E E T U E O E D V F D P P P C Z E O A I T V L X D O I E U E N C L S R A V Y I E T O L S L R O A S V N G E F E H G E R S I S N N A A E E S I O I B D M S T F R I N T I R E N A Y O E O A T E E

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l SLA E M S S A O S H P E T E S R N I R A N N R O S G O S D I E L O P H A O A I R P E D T I P N S C N A R G E P I U C A N V O E O U D I R E C V O I F N T U C L E I E R T O R B V H C F E G I U A S N E T E S D N S O G A D P L N N I S B I E L H L A T A T O S L I S L D I R T I W N S E C N M A E D T N I A T T A S F V N N I E R F O R A I i E E T D C S F E D C S O U t A O M N N T E H S R E I O D V H E A A N G H C F I R P E L L E N T A G I E N F V E P E N L M I I E T N E I S S O O O T I E L N I I C M S D N I H S E T V E E T E S T T C R V D E I W I I R D S E U M E E S V X V O G N Y P S E R Z M O E E N F N A S S T P Y E B N E S L T A E R AL S R Y D I N Y N A S H I E I S I N Y D T E P E U H H L D P M T E F A S E T E U O A A C E C E P N D I L S R O O H R T S R L I E T R O G E V F O T O L I R N E S T W O L O R R O E E F I R E T C E T V N N F H P Y S E Y D N E O LP M E P T N A P T I E D I M A F G E I I S E C M T O R O E , N F R F C P S A C G H E I A R E E A A I N C O G T S T S O T Z S U O I O R N O S F I I F Q I L T P I P E F R R R O E T P A M U R T O D C O I D E S E U E G E E R C I S P D N R F E H C O I E C S O E O T T J F E l 4 R N I N A i H t D A E A I I H E A I A A P L E A P H T I T C O U M S T E L H R T N A S T Q S 4f T V N O C E L E G A G 4 o M L E S N L N t R I P E O G I I I C I l V T F C P I l l V N l I o N S O W C N R I T I I I E U S 1 N E T E L T C G E S I P N B E T A I C E E S T H I F S E V A L E S N S B L T D U R F E D O E H E H S A i l t T D T R T A L A l S E S O E D I I E F D AH F R I T L I D D A A G t tA O L I N T L M U G I 1 W P O N I I E N O A W A T S I L R D S A L - O E H - O l t F A T P F %O LON /s 4 t

PHASE II - PRELIMINARY DEVELOPMENT PHASE - IN THIS PHASE, THE EFFORT WILL CONCEN-i TRATE ON DEFINING AND DEVELOPING PROPOSALS TO MODIFY THE EXISTING SURVEIL-LANCE PROGRAM FOR REVIEW AND CONCURRENCE BY THE COMMISSION INCLUDING: i I - FURTHER DEFINITION OF PLANT EQUIPMENT ASSIGNED TO EACH OF THE i SURVEILLANCE CLASSIFICATIONS PREVIOUSLY DETERMINED. u - DEVELOPMENT OF A PLAN COVERING SURVEILLANCE INSPECTIONS OR c>s TESTS FOR EACH SURVEILLANCE CLASSIFICATION. - DEFINING THE FORM IN WHICH THE MODIFIED RULES WILL BE T ISSUED. - DEVELOPMENT OF CRITERIA FJR ACCEPTANCE, EXEMPTION, REPAIR, AND REPLACEMENT, PERSONNEL QUALIFICATIONS, ETC. c5 'hJ - DEFINING RESPONSIBILITIES, EXAMINATION TECHNIQUES, RECORD KEEP-ING/ REPORTING REQUIREMENTS, ETC. - r ( M )

PHASE III - DETAILED DEVELOPMENT PHASE - IN THE FINAL PHASE, THE DETAIL RULES AND REQUIREMEllTS WILL BE DRAFTED, SUBMITTED TO THE COMMISSION FOR APPROVAL AND ISSUED TO THE PLAT 4T FOR IMPLEMENTATION. REQUIRED REVISIONS TO THE TECHNI-CAL SPECIFICATIONS WOULD ALSO BE PREPARED FOR ISSUE BY THE COMMISSIOl4 WHEN PSC IS PREPARED TO IMPLEMEllT THE MODIFIED PROGRAM. u Ch N u. cs Fgi i s .a -a q

N L O A R I E N O T D R O O F I I N E T I V U T D I Q G A E F I E N R R E R D E R I I D A U D G R Q L N O W E A S A I C O R I T C L T S A L S I E A T N N T T S I I N L E A D E L T E R I H V N M A P W R T O I N U N F T O Q R S O S I E U N T T O S T C D T R I E E N T L O C U F P T I E S A E S S N L S P E R A E I S R O I M H R H N F A P E T I E R C Y H Y G N I T F T H O O V E O P R I R F N G O P T E A O T N S I S S I N I O W N N T E D L L C T N I E I I I F L N X A H V E G A U E T P E D N F N S G D O R Y D R I L W N Y N I E T E A E T A T D E W I I S I I Y E A N F E T V F F E C U A I I A E I S V I E I N R S S R F R E S G I O T R I R A R E S F N O L D S A E I F C E A S L B H E L I P H E T H C S L C V T A R L A L F E B A I O O O F C E W R V O N A L P N E A C P I C N L E U R A N O L D N A D A S I I I C L T T E V E F S U R A V O H P O O N R R T E W P U P H I E M M S , T H S I R O E T T E H T S M N E T C A O E H E A H R M T D E P F Q uCN N O ;~ f

PLANT SAFETY PLANT SAFETY DBJECTIVE - ENSURE THAT POTEfR2 AL RADI ATION EXPOSURE TO PERSONNEL BOTH ON-SITE AND OFF-SITE ARE WITHIN ESTABLISHED LIMITS IN THE EVENT OF: u ENVIRONMENTAL DISTURBANCES N - POSTULATED ACCIDENTS INVOLVING MALFUNCTIONS OF PLANT EQUIPMENT dw c, 4 L 'l L 'l

T N E D E D O N V I A E Y V T E T O N H D , N E R Y W T N S A F P T O A M A I D E E F S H L T D E T O C I U I R B H V O S D I Y S N H A S 0 C S E A W n. C E A P E , N H E H HT S E T S T N E U L O I E P R Q A H E I E U E E T D T T S H I I E C N E V - K U O C R O P A R E LO R C I T L P E Q T S E B S K RT L H U N T T P O E D N A N O V N I Y A E E T I A C O T L T H C M E P A T N - E E E F G U R R R T F L O U A Y I S B T C O C T T I E Y R A A T D M F T T R R E N E F E N O E H A M O A F O T P L R T A C C M Y P O Y S A E 4 F T L Y E T L R C E R T R O L E A S A I L D O P R E V E E C H E L I H U R S C V C T T F O L D U C F E N I R U O H A N A N W E W N N Y F I T D C R O O AT T C S L I D I I N T J S ET T EL N U N C' A R U N R I E F E C B O H O O B P S N C S C C A S N E O H E O S P C E i R R O M I T H O h H O C T C W T F N U F YT E F A S \\-(W %5 wN~ }] J tC~

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O TN Y I T E R S F R E E A A P R S S U F E T O H C T S T U A R E H T C D T S N E I A N W D T I N R F E A O E R P D E N S M F W I E R O T N R E D E E A T T G N V) N U N O I I ) I H I S L I S P T M A T D E O R O Y O L S N L O C T C E S E U I R A N O T I L O C C E V S R C P S A R I M E N E O T Y M I T E E Y O G O R C C E T H T C A I A F S T E M T E E O A Y F , A C V T I A D S S O A S D N I T S M U T U A Q R T_ T E R F I N N G R T O S E A A N A S Y O D E I S Y E T P A V L L P P D F S R E I R U F H H S E O D , L A T T S H C N S I S I I E T C A E A W W C A R F C X S I U I E E E E S T N S R R D N S C E A E E E O S U H B F F S S I A R W R R A E V I T L T E E E E C I N D A C S I H T T L A C ( T N N E Y S I I R B R I R A F T S S F U S I E M A C T F S F E L S S A T C E I I I C I I V A S I I D S L Y N I F C R T T A L A N E M A E O S A F R T H W F L A O t T T( P S F t EM N O A B R I VN W E M:. hN {$ e

) E ) B S E O E S M A ( S S R O I S ( O R R E E F F E E K R E L T A T K D D B I U S A E E A R Q U R TC E C H D Q I T L N H U E B N Q T G R E O D T I I E R N O E O D N A I R R 1 E Y T E A O I T P A W A P E I O S G R S T A E N E N C R R E E L I L D W N E A B R L S I O A D E N O U L I D F E H O F F B E C I E C W T C C S L M E G C A U O C I H N X L H T A H A O E D A S W R T I T N T E D T F R A T U N R N S S O R U O O E U U M U F E O R Z F L O E M) A I R T T P H G I I ) S D O T R S A G L O F C S E I N D W A H D L I S( G N T N R A S A) N L A O T S( O I S T T O A T N S D E S D Z T S E O A G A O H G Z L N N D H( I T R T T A C I R I M R L O O O ) E I I D R W D H H W A O Y O T E A A P D H T O U O N G M O E C N N S T R T E G F W M O 5 2 F A N O I T E E T 0 0 E A 1 S W D N T L 2 L S O T I B N B N R D U O C A G A U A T H ( I I S U S E S E E T E F H S S B E B T B U S S E E S D O D O S E F C A T T H S E A N L S D S T O F S A C U N ) ) U I ) H A B M A A B M W A T S A R Y U T T E S F 1 I I A I I I D S I L R A A T S N F E M N O C R I V ~ N ~ E a, {', { t

ENVIRONMENTAL DISTURBANCES (CONTINUED) - TO WITHSTAND THE EFFECTS OF A RAPID DEPRESSURIZATION OF THE PCRV, A STEAM /FEEDWATER LINE RUPTURE OR A LOSS OF CONTROL ROOM COMPLEX AIR CONDITIONING IN COMBINATION WITH OPERATING OR TRANSIENT LOADS WITHOUT UNSAFE DAMAGE OR FAILURE TO FUNCTION. A) SST - 300 MPH TOTAL HORIZONTAL WIND SPEED. D. PLANT ITEMS ARE DEFINED AS FSAR SAFETY CLASS II IF THEY ARE NOT INCLUDED IN THE FSAR SAFETY CLASS I CATEGORY. E. FSAR SAFETY CLASS II ITEMS ARE DESIGNED FOR THE FOLLOWING CRITERIA: u ((, I. REQUIREMENTS OF THE UNIFORM BUILDING CODE FOR SEISMIC ZONE I (1964, SECTION 2314). lb4 II. DESIGN WIND VELOCITY OF 100 MPH. 4

0 E S , R P E - S U E V R N T E I E O A K R P I E D D T F O E/ D T L S N I D R L D A N O D O O O J E R R Y C A D T T I N L M I T V O O L N G O C R I E N R N T B D I P U N A W O P I C O E M C A R C L R O C E A L A R E N O F H S N D F L T A I E O E H M T E R R T E A H T O L T N C Y E V U O G D I T Y C E R I T S B H E V C O Y T N O A P D T E R E I G P N Y R D V N N A T E I I I O M T T I E N E D V F N O N C C S T I A U R G A E S S S P I E T Y S I E S R O F S N T V E E R O N I R D F P F N I A T A O O W T L C T S O C P E S N S U E D N J N A N H S T U B O L A T A U F I P L E E H O T O M N L S Y Y C E R W E T T N H T T O R E E E U T N N D V F F F O E T O R A A O C D U T E S S Y T N H S l T N Y E S E E R T P U R I E E I I l I E E D E H F l E T A D V D R E H N O P H T D S E I I C U T I E T T C V C A C T M I R A O E A D R C E I S O E W H E N O A H A P R T T H A F D C B R E A O T E C A O H N L T T I U T S O P t ((' y N

POSTULATED ACCIDENTS (CONTINUED) - CORE AMIl E11EL TEMPERATURE CONTROL FIVE INDEPEf1DEf1T MEANS OF FUEL TEMPERATURE CONTROL ARE PROVIDED TO KEEP THE CORE COOLED AFTER SHUTDOWN THUS PROTECTING THE CORE FROM Uf1 CONTROLLED HEATUP DUE TO RELEASE OF ENERGY FROM FISSION PRODUCT DECAY. FOUR SEPARATE FORCED CIRCULATION C00LIf1G LOOPS AND A BACKUP CONVECTION / RADIATION C00Lif1G METHOD PROVIDE THIS CAPABILITY AND PERFORM THEIR FUf1CTION IN AN ACTIVE MANNER. ACTIVITY AND RADI ATI0ft CONTROL THREE INDEPENDENT MEANS OF ACTIVITY AND RADI ATIOff Cof1 TROL ARE PROVIDED TO KEEP RADIOACTIVE CORE FISSI0ft PRODUCTS C0f1FIf1ED THUS PROTECTING THE PUBLIC FROM UNCONTROLLED EXPOSURE TO RADIA-TIOf1 DUE TO RELEASE OF FISSION PRODUCTS TO THE ENVIRONMENT. tg ((3 THE PCRV LINER (PRIMARY CONTAINMENT), THE PCRV STRUCTURE (SEC-ONDARY CONTAlf1 MENT), AND THE VENTED REACTOR CONFINEMENT BUILDING (TERTIARY CONTAINMENT) PROVIDE THIS CAPABILITY; 01LY THE REACTOR b C0f1FINEMENT BUILDING PERFORMS ITS SAFETY FUNCTION IN AN ACTIVE g MANNER. O

POSTULATED ACCIDEflTS (CONTINUED) - SEEIR EUEL TEMPERATURE CONTROL TWO INDEPENDENT MEANS OF SPENT FUEL TEMPERATURE CONTROL ARE PRO-VIDED TO KEEP THE SPENT FUEL ELEMENTS COOLED DURING HANDLING OR STORAGE THUS PROTECTING THEM FROM UNCONTROLLED HEATUP DUE TO RELEASE OF ENERGY FROM FISSI0f1 PRODUCT DECAY. TWO SEPARATE SPENT FUEL COOLING LOOPS PROVIDE THIS CAPABILITY AND PERFORM THEIR SAFETY FUNCTI0ft IN AN ACTIVE MANNER. SEEld EUEL ACTIVITY AUH RADIATION CONTROL TPREE INDEPEllDEtlT MEANS OF SPENT FUEL ACTIVITY AND RADI ATI0ff C0flTROL ARE PROVIDED TO KEEP RADIOACTIVE FISSION PRODUCTS CON-FINED THUS PROTECTING THE PUBLIC FORM Uf1 CONTROLLED EXPOSURE To hN RADIATION DUE TO RELEASE OF FISSI0fl PRODUCTS TO THE Ef4VIRONMENT. 'W THE FUEL HANDLING MACHINE OR THE FUEL STORAGE FACILITY, THE GAS WASTE SYSTEM AND THE REACTOR C0f1FINEMENT BUILDING PROVIDE THIS lI'# CAPABILITY; ONLY THE FUEL STORAGE FACILITY DOES POT PERFORM ITS > kE SAFETY FUNCTION IN AN ACTIVE MANNEPs l

S R O D T E D A D I E R N L E I E A P T R A t N N P A S P E W U S I F P G O S N U D S E G S M T i R D N A U A' E N h E H L T O I S A T S C A C U E S W T L Y E R N S O A T R O W T M E I O R F F R D O A E D L T E N S R TO A 0 N I 0 E L F R W C M P O A E D P P S T E N I U S F A E O U S S S F Q O G N I T E R L N E J A E ( I D S T S N E L I A - U O V U I C W C I R S D G N R I S E N W , D YT C A E I O R E L F L D E L F D C O L T E A E D O 0 A E S C Y N C 0 W H R T A C D W T O E Y E S N F F S C N E N R A A E N O F O OT T L S V E I P I G T J L A G R R R A T E R N A D E L N P E I S M U E N L F R E C M R E O O R P O GT O D T N I I S C N A O C U A M Q L A E A L I D N U T D E U E C A E C T O h I M Q R L C I R S U R I I D S I i T S C C O C O {H U A R F S T S M 1 L M i I l L S C U C) A U D G L I E 0 I 0 L Y L HN C L I I E L C A T E E M E H C L R H P E R F R O A P R O A O O O S O U l D S T F C F T S I C N W I I O I D T U H S AhN LC ND%

!!! - SAEE SHUTDOWH EMERGENCY COOLING - (PARTIAL LOSS OF FORCED CIRCULA-TION EMERGENCY COOLING) FORCED CIRCULATION C00LDOWN USING ONLY FSAR SAFETY CLASS I EQUIPMENT. FIREWATER SUPPLIED TO HELIUM CIRCU-LATOR PELTON WHEELS AND TO STEAM GENERATORS. IV - BACKUP EMERGENEY C00LINE - (COMPLETE LOSS OF FORCED CIRCULATION COOLING MODES) CONVECTION AND RADIATION C00LDOWN USING FSAR SAFETY CLASS I PCRV LINER COOLING SYSTEM EQUIPMENT SUPPLIED WITH OUTSIDE POWER; STANDBY POWER OR BACKUP ACM POWERJ SERVICE WATER OR FIREWATER SUPPLIED TO PCRV LINER COOLING SYSTEM HEAT EXCHANGERS. dh 'es y a

EMERGENCY COOLING DESIGN PHILOSOPliY_ - A SIGNIFICANT DESIGN FEATURE OF THE EMERGENCY CORE COOLING SYSTEMS AT FORT ST. VRAIN, ASIDE FROM THEIR DIVERSITY AND REDUNDANCY, IS THAT THEY UTILIZE, FOR THE MOST PART, EQUIPMENT THAT IS USED ALSO IN THE NORMAL OPERATION OF THE PLANT. SEPARATE BACKUP ELECTRICAL POWER SUPSLIES FOR THIS EQUIPMENT ARE ALSO PROVIDED IN THE EVEl4T THAT OUTSIDE ELECTRIC POWER IS Uf!AVAILABLE. - ONE ADVANTAGE OF THIS DESIGN PHILOSOPHY IS THAT NORMALLY OPERATING EQUIP-MENT OFFERS A HIGH DEGREE OF ASSURANCE THAT THE SYSTEM CAN PERFORM ITS SAFETY FUNCTION UPON DEMAND. IT ALSO ALLOWS A DISTINCTION TO BE MADE, FOR PUhv0SES OF SURVEILLANCE, AS TO WHICH COOLING EQUIPMENT S.0ULD BE SUBJECT TO FURTHER INSPECTION OR TESTING. u C7s N N@ t>\\

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EH T T N F A O T S S L A S S N I P S D A E M T R F ) E C R R A S H N O O U T M T E F F G S S E U R E U R T N Q E E F A O S I E P H A H T Y S T S X C S S N O E I / M O T F D R S E C O E M T S E T ) R E S E R S E Y T E T E S R U Y H L R E S R R U T S T N A N Y O S A O P I S W T O E R E( G O C L F O T S N N L I C A Y A E O F R I T Y Y S G L D S T R S R T E I I E R T R E A A E E A A D L M T R D O F U I D I E A A T M M I S A I V E T T W W 0 L Y E O R O I N S D O C Y T D F T P R F E Y E L E S V S E F S E E P I F E F R N Y D S A E G L E S S E G P N N V D M A R N M R O O L S E I I I U O I I A N S R I T E L A I E A V N T C D D T T T V TN G D M O E S E L A A A A N I R M Y E S I R R R R Y L E E R P P S R E U E E T T T A H B T N E E E P S P I R O E U R T A E N N F O H D R Q O H R S W G E E A ( T E A E C O R/ P P S T E M M D S I S Y I Y S E H R C T A A V V V D F V E D R W A A L E E R R R T T C C C O H R U S E I R I A S R T A T N F R F S S P P P U S P U A G G E I E E D E E E E E G A N E F S H H N H H H H H E L N F C E E O F E T T A T T T T T A X D A E I T S I O S S O B I D T C S T T 0 0 0 0 O O l D E J N D N R t A 0 E D V S U E E A G I R E A T F R R L N U G T c S H N E A P I E f F E Y E D F N N H D T N E N R O 1 C I E I R I A I I I C F E E A C S F G P. E N E H C A H R C l l D D E T W A S E T V A ER E I E I I N I G !E at E) e p ~eM

S E D I R F N O O O E U N I T C G S O D N N Y A B I T E A A E E I L E R R D H T I T C R E R V I E C E G R U V C Y T E S T I A B O T E S S S R N H ET R S N D P I T E I E P R C A D R E G H N T O X T I I N F E R V E T I E O H L A T F C R T G L L A O P N O O G D I R O S E N Y N T T C D A C N D S I R A R A E O R A E U E Y T C O U L D R R O T G E L A R Y C E R T A D P B A F N N E A E E Y U Y R R S H M T O B O T N E B E D O F R Y H E T R A E E R T R S I G R H A E N V U T D F E I N E S I N O N A E H S E U C T E O S I G A E R D B N N H P P E O E N T U H E I O K T S R T O C N I U R E I H T T A A L S O T C B L P S P E S O M E ) F T T Y O O R F D O O C E C C P I E R U H C U N P D T R A T S N O O O N T P R , T S A C I I C I L U D T T U P N N C K E A O D E E S O O H O O N C N I R I C R C C I U A O ( T F B I H P A C S ; E T R E S N Y E S S H O N R D U T D I N T T O 'B C I I F O R F E I , S A S E A F V U Y A O E T N M E S R A G T S R V I G E R I T F D E E P I I F F E T N S S E Y A A H O C O E Y H F R S S T T A C D S T O A D E R I E I E I N I G N E J (CN 1J AN s NDe

Y S S C T E M N - A G V T A H N I E R E R I H O G O X G N T I R E T F R N U N O L D H R I I S O E R E A N E M E T T E O R E T I P E H R A A R C O T A T O R L U T A W D T N T E U T N A R E I O C P C A W L A G A O R E O U P N N I H T Y E I F D C E I IF G A L R L C T R S L R E U L E A E U I O E D O U T N M D S H C O O W I R E O S W C O H C A S T R R A O C H T T P A T N R T L N E A L I A C P R O A E H L E E E R F E M D T P V R R N I I I M D D S C I E R E E R A C E W T R T A C D D H O H P L D S U R E N T F S E H U Y G O D A E E D C M R H D R H N A O S E F I I E , T F V S M E. U T Y S A G A D O M A F , S R L N S E R E F I T P T U E O E P O U I L D A S E Q F T O T C G O E C E Y D E Y A O A R O R I R S I R Y T R L L I i f I A U C I C E D E V T L E E W T O N E L P T C 0 Y N D N R O F I E N R F A B S A I O T A P I 0 C I I L T S A L C C N G A E N O O C P E O S Y G E S F O T N E A H O M E I C U H C T C U C C R A N E N D F T I R E M A S D Y E E F E L U G E N L R N Y H O L E O T B H S ) R D O U A G T E G T A D E N E I O D I E M O R T W N S F N E S L D E I C I O N L U E I E C O E A N T D N M C D S L N S S A P U E E O A N I I I N A I T O L S F T S E E O H O S T N I U N S R H C N C D N L O T C O Y Y D A T E N O U C A R C T S N E E A I M ( L I E A S D R O S T U C T F G M N O T E E C D S C O A N Y E A C H T E N D R D N S I R T D T A S A R I E L A S S Y E R A C C S E O M Y N C D A R S P E E l S O D 4 M O U R I rE A M E F I G D O A C R I F E F , S F Y T G E S S L F C R E R C R E T N P A R E A E R L A N E R S O A P I U M E Y W R U S O H S H O A F T F T C M L F E W S T T S G N I R V E I E N I G N E uCN N L:

R N N R L O I I O L Y - D T A E - A T E R N E C M N K E T O E C W A O A D A A A E F R I E O U H A E R D H A M C V R T D O T S C P E T E S I O E H R R A R V E E F P R S R E D R T, D F R D O E T C E P H N E R N E O H N E P R T A D A O R A I S S T E H U c I E I E S N N T M T E S I F N S T E E O S N H O O O N S I N C I I S T L E I O E D I N A C S A E C R N T C D D G E R A N U V T L E T T F U O C I O O R N A O Y T I E T V E C N C U O R R C T T O O N E D S T S C T S A U C O N R I S E T O E T D R N R P E N R N L Y N S N T U P S R O E C O T O E C R E I O S F I R F M A P S C T S D D O f N Y M N E T Y N T L E I E H O S N R E I A T S H I R I F hE A A R C C E A N A N T N H T M P I N M M O, T L O I F C E H T O E I P T O T 4 I i0 R E M N I N R M N R T T E C P H E T I P O E E - E A N R T T M A F C M C Y R G E A Y N N N R N E N N T A I M R O O A I T O H D O I E T E L A E C T N R S F S I N D A A R M I N M D O T N A I I A. U O N E R E V , S E A A T R R L. C O P O C R N R T O N T P T C N E E E S L T I H V I I O N E R V T O Y R N S T G E F Y C E E U : M H F T R C E A N W T L Y P T P Y C A P M E I O I D N W K H N O R I R A D N A U V A E N E I G R , A R 9 R O H A N E O N T ) D Q O S C I D W D N E S C M C T T D I N A E O D P 2 G E N D I U C L R b N S D O L V E R T A O T A C F Y I N C N E A A E B I I S N U H N E A U R A U E E G T T H T O G T E I H D B P I I E R A T E E R E O S T N D O N T F D U T R T R O P F R U C A C A N S N U N O T O A P A E T E T R S H C ( N S A S O T Y U E C T C V C S P O X N I P D D E I S N R F D R R N U A D E A E E P G E R , E A E A S S R M M Y R N N M T Y R G R N G T I N S R N N E R N , N T B E A N I I I S E A E O A E I U I R E L N P I H D N T D D D A E G A P D N A I I L R I V L P T T T T L N I E T E I A C G D F N E D G R O N E R I I I N C O S O R 7 Y U A N N U U C A O H I S C T V E P C A C C T B B T E A B G A D E R V E E N I GNE A [ - ( -

E E R H P D T - I I U F E I D N R Q L D I P E A A N S D S O S E E I A R L H I I L T T W I F A D T T T D N L S A A E A N H T M I I E P T N S D D I U E A E I V Q T W S O E O O R P T P P S I O I S R D O H S E P R T T E C A R N S U T P I I G P S E N A X U T FA L E S I S P L P D S E M N M N D H O A O O E T C O I R T R T E N M C C E I O E E N N O T S U I D R E E F G E D H N L L T Y E L O O T A R T F E N T T O F A S N Y A )D N O T S S S A A C I E I U L E A R D N N E I I E H B A M E T E T A R I N N B E O F O O R E L F I I S O H B R S C ( T A F T A E S C H C P A S E N E L D T T O D D O C R O N I I E T A R E T V T E U P M C O S Y B G P E R E L T P G I f E E I F R U O N R 4 Q R O O A 7 I S F E P T C DE R I E V E N I 3-NE UCN N e4 l l

E - E T C D R S N E E I E A F R U F T R A I Q O E U S U E M D S Q R Y N G I N T M N S E E T O A A A R R D E I S I E R A N S F T N E F A A O B I G N G N A I O O N S E S S D I L E H S A A T S R I I P T U R W E B T R I I S C N U L N G D T T S U G A E N T I G E I N P T C N R N L D O N I S N U O I P / C A T T N O R I E U N L U S I C T T C N R O E P O E S C N I E I N H T E A N A T W T I E G C D U L N O A L H U E N F L O P R E T O D I N V D A I C O S R A T H A R I Y E R I E V , T V A A R B A T N S O S E R E E H O N R M F U N L T M T N I I P E A S O C E O O T T S U D R E I C D O S C E N F C T I C F N I E E T Y R P S S I F N F O S A D I E O R R N S O S E N P I , H C D N O U O L O T S C I O S T E I R N T P V E I C S T A A E E P I N M S E V C A E R E D C F F I E R N O H E L E E L A V H V O F S V N T D A S R T P R I I E I E E N M E L T T A D T O A E S F T O P B C A T A I N O S C A E U N Y L T N I O T J Q I L E I I E T D T S B E A R R D O D M A - D D N S R E E I O O T E O A E Y A E A P F A L L T E G T N R R L B L T N N E E E I D F D A I R A A I V U T E A T A P A R L W E R E I I I D E T B V S V N T L M Y A M R N A O O I S L A T V A O E H S R F R A I P 0 P M A R E A R G T T R G F G N R E O A E O I O V R S R R O O 0 F O P A P S T T D E G A D E N E H N H N H E T A T M S T I O P O R E P S O P R U P g {, p c

1 PHILOSOPHY - THE DEVELOPMENT OF RULES AND REQUIREMENTS FOR SURVEILLANCE OF SAFETY-RELATED EQUIPMENT AT FORT ST. VRAIN WILL BE BASED ON A PHILOSOPHY WHICH CONSIDERS THE CONCERNS FOR OPERATIONAL READI-NESS OF SAFETY SYSTEMS AS WELL AS THE CONCERNS FOR INTEGRITY OF THE REACTOR COOLANT PRESSURE BOUNDARY. THIS PHILOSOPHY RECOG-NIZES THE IMPORTANCE OF VERIFYING PRESSURE BOUNDARY INTEGRITY TO PREVENT THE OCCURRENCE OF A FISSION PRODUCT RELEASE ACCIDENTJ BUT IN ADDITION IT ALSO RECOGNIZES THE IMPORTANCE OF BEING ABLE TO MITIGATE THE CONSEQUENCES OF ANY EVENT WHICH COULD ADVERSELY AFFECT PUBLIC HEALTH AND SAFETY. FURTHERMORE, THE PHILOSOPHY RECOGNIZES THE GENERIC DIFFERENCES BETWEEN LIGHT WATER COOLED REACTORS AND THE FORT ST. VRAIN HIGH TEMPERATURE GAS COOLED REACTOR, PARTICULARLY THOSE DIFFERENCES WHICH PROVIDE AN INHER-ENTLY SUPERIOR LEVEL OF SAFETY. u Ch N N Q f-e ,e a ww w.we w -= -O .e e-= e= =m e.e - w.e-w ea

PHILOS 081Y (CONTINUED 1 - THE BASIC APPROACH TO BE USED IN DEVELOPING THE RULES FOR FORT ST. VRAIN IS TO ESTABLISH A PROGRAM THAT WILL CHECK THE CONDI-TION OF PLANT STRUCTURES, SYSTEMS, AND COMPONENTS ON A REGULAR BASIS TO A STANDARD OF ASSURANCE COMMENSURATE WITH THE IMPOR-TANCE OF THE SAFETY FUNCTION OF THE ITEM. CLASSIFICATIONS WILL BE ESTABLISHED TO PROVIDE THESE LEVELS OF IMPORTANCE AND APPRO-PRIATE SURVEILLANCE REQUIREMENTS (I.E., TESTS, EXAMINATIONS, OBSERVATIONS, MONITORING, ETC.) SPECIFIED FOR EACH CLASSIFICATION. THE SURVEILLANCE REQUIREMENTS WILL BE BASED ON, DEVELOPED FROM, AND ENHANCE THE EXISTING SURVEILLANCE REQUIREMENTS CONTAINED IN THE FORT ST. VRAIN TECHNICAL SPECIFICATIONS. u Ch N l[h O

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M-THE PROPOSED INSERVICE INSPECTION AND TESTING PROGRAM WILL PRO-VIDE RULES A!;D REQUIREMENTS FOR SURVEILLANCE OF PLANT STRUCTURES, SYSTEMS AND COMPONENTS AT THE FORT ST. VRAIN NUCLEAR GENERATING STATION. THE RULES APPLY TO THOSE PLANT EQUIPMENT ITEMS WHICH, IF FAILED, COULD INTERFERE WITH REACTOR SHUTDOWN, INTERFERE WITH REMOVAL OF DECAY HEAT OR RELEASE EXCESSIVE RADIDACTIVITY TO THE ENVIRONMENT. SUCH ITEMS ARE GENERALLY CLASSIFIED AS " SAFETY RELATED" AND INCLUDE EQUIPMENT DESIGNATED "FSAR SAFETY CLASS I", " SAFE SHUTDOWN", " ENGINEERED SAFEGUARDS", " STANDBY POWER", " EMERGENCY COOLING", " BACKUP EMERGENCY COOLING", " FIRE PROTECTION", ETC. u CN N N %I gg G4 m =,e =aa

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SC0pE (CONTinuEId_ - THE PROGRAM WILL FURTHER CLASSIFY SAFETY-RELATED EQUIPMENT ACCORDING TO THEIR IMPORTANCE TO PLANT SAFETY AND PROVIDE THAT EACH EQUIPMENT ITEM BE PERIODICALLY TESTED, EXAMlHED, OBSERVED, CALIBRATED, OR MONITORED AS APPROPRIATE. THE PROGRAM WILL PRO-V;DE CRITERIA FOR ACCEPTANCE OF RESULTS, EXEMPTION FROM REQUIRE-MENTS, REPAIR AND REPLACEMENT, AND PERSONNEL QUALIFICATIONS WHERE APPROPRIATE AND WILL DEFINE RESPONSIBILITIES, EXAMINATION TECHNIQUES AND RECORD KEEPING / REPORTING REQUIREMENTS. wm ~J -21 3 4 ~

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