ML20213D951
| ML20213D951 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 05/07/1987 |
| From: | Nerses V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20213D919 | List: |
| References | |
| NUDOCS 8705140417 | |
| Download: ML20213D951 (57) | |
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. e f" %, UNITED STATES e; . / *t, NUCLEAR REGULATORY COMMISSION j ( ,g wAsmnoTom. o. c. aceos Y f .
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YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATION DOCKET NO. 50-029 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.104 License No. DPR-3
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment by Yankee Atomic Electric Company (the licensee) dated February 5, 1986 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendmentandParagraph2.C.(2)ofFacilityOperatingLicense No. OPR-3 is hereby amended to read as follows:
l 0700140417 870D07 9 DH ADOCK 0000 F
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O * (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.104 , are hereby inenrporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance.
FOR E NUCL AR REGULATORY COMMISSION c , Acting Director Project Directorate I-3 Division of Reactor Projects, I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: May 7, 1987 l l l l l l
- ATTACHMENT TO LICENSE AMEN 0 MENT NO.104 FACILITY OPERATING LICENSE NO. OPR-3 DOCKET N0. 50-029 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. Th revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of ch9nge.
REMOVE INSERT I I XV XV 1-1 1-1* 1-2 1-2 3/4 3-27 3/4 3-27 3/4 3-32 3/4 3-32 3/4 3-37 3/4 3-37 3/4 4-15 3/4 4-15 3/4 4-16 3/4 4-16 3/4 4-26 3/4 4-26 3/4 4-35 3/4 4-35* 3/4 4-36 3/4 4-36 3/4 4-37 3/4 4-37* 3/4 4-38 3/4 4-38 3/4 5-3 3/4 5-3 3/4 5-9 3/4 5-9* 3/4 5-10 3/4 5-10 3/4 6-7 3/4 6-7 3/4 6-8 3/4 6-8* 3/4 7-30 3/4 7-30 3/4 7-33 3/4 7-33 3/4 7-35 3/4 7-35 3/4 7-38 3/4 7-38 3/4 7-39 3/4 7-39 3/4 11-1 3/4 11-1 3/4 11-4 3/4 11-4 3/4 11-5 3/4 11-5 3/4 11-6 3/4 11-6 3/4 11-7 3/4 11-7 3/4 11-10 3/4 11-10 3/4 11-11 3/4 11-11 3/4 11-12 3/4 11-12 3/4 11-13 3/4 11-13 3/4 11-14 3/4 11-14 3/4 11-15 3/4 11-15 3/4 11-16 3/4 11-16 3/4 12-1 3/4 12-1 3/4 12-2 3/4 12-2 3/4 12-9 3/4 12-9 3/4 12-10 . 3/4 12-10 _ _ . _ . . . . . . . _ _ . _ _ _ . _ _ _ . . . . _ . . . . . . . . . . _ . . . . ~ _ . . . . _ . . ~ _ . . . . . . . .
r _ ATTACHMENT TO LICEi1SE AMENDME!!T NO. 104 - OPR-3 8 3/4 4-13 B 3/4 4-13 6-8 6-8 6-11 6-11 6-13 6-13 6-14 6-14 6-15 6-15
-- 6-15a 6-16 6-16 6-17 6-17 6-18 6-18 6-19 6-19 6-21 6-21**
6-22 6-22
- Overleaf pages included for document completeness. No changes on these pages.
** Repagination only. No changes on this page.
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.[ _ _ _ _ _ _~ _ '_ [_'_I ~_[ *_ _ _ . _ _ _ ** *1I"""[ I *_______.__1'_______'____________*
i ? INDEX DEFINITIONS 1 l SECTION PAGE 1.0 DEFINITIONS D e f i n ed T e rm s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 - 1 Thermal Power.............................................. 1-1 Rated Thermal Power........................................ 1-1 Operational Mode........................................... 1-1 Action..................................................... 1-1 Operable-Operability....................................... 1-1 Reportable Event........................................... 1-2 l Containment Integrity...................................... 1-2 i Channel Calibration........................................ 1-2 i Channel Check.............................................. 1-2 ! Channel Functional Test.................................... 1-3 , l Core Alteration............................................ 1-3 l Shutdown Margin...............................'............. 1-3 Identified Leakage......................................... 1-3 i Unidentified Leakage....................................... 1-3 , I Pressure Boundary Leakage.................................. 1-4 Dose Equivalent I-131...................................... 1-4 Staggered Test Basis....................................... 1-4 . 1 i Frequency Notation......................................... 1-4 ! Physics Tests.............................................. 1-4 i i E-Average Di sintegration Energy. . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 Source Check..................."...........................
. 1-5 YANKEE-ROWE I Amendment No. ,104 **********44o=* w e+4. . +w . ee. ee e. .mww,. ., % ..,% , , , , , , , , , ,,
- i. .
,1 1 i t I INDEX 1 I ! ADMINISTRATIVE CONTROLS , t + ' PAGE
$ECTION , ' Consultants........................................... 6-10 Meeting Frequency..................................... 6-10 i < i.
i 6-10 I Quorum................................................ ! j
- l. Review................................................
6-11 l l Audits................................................ 6-11 I j l Authority............................................. 6-12 1 1 2
! l l
Records............................................... 6-12 i l I INDEPENDENT AVOIT ANO REVIEW............................. 6-12 I 6.5.3 j i - 6.6 REPORTABLE _ EVENT ACTI0N.................................... 6-13 l .' 6.7 SAFETY LIMIT VIOLAT!0N..................................... 6-13 6.8 PROCE0VRES................................................. 6-13 ; 4 6.9 REPORTING RE0V!REMENTS 6.9.1, 6.9.2, 6.9.3 ROUTINE REPORT 5............................ 6-14 I I 6.9.4 0ELETE................................................ 6-16 l I ! 6.9.5 UNIQUE REPORTING REQUIREMENTS......................... 6-18 1 6-22 I SPECIAL REP 0RTS....................................... 6.9.6 , i 6.10 R ECO RO R ET ENT I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-22 [ 6.11 RA0!ATION PROTECTION PR0 GRAM.............................. 6-23 i I t 6.12 HIGH RA0!ATION AREA....................................... 6-24 4 6.13 ENVIRONMENT 00ALIFICATION.....................< .......... 6-24 , t
, 6.14 PROCESS CONT ROL PR0 GRAM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-25 l 6.15 0FFS!TE DOSE C ALCULATION MANUAL. . . . . . . . . . . . . . . . . . . . . . . . . . . 6-25 ! 6.16 MAJOR CHANGES TO RA0!0 ACTIVE __LIQU102 GATE 5US AND SOLIO WA3TE TREATHENT 3YSTEMS. . . . . . . . . . . . . . . . . 6-26
+ f i 6 XV Amendment No.,A6',)d 104 f YANKEE-ROWC i i
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r a # 1.0 OEFINITIONS DEFINED TERMS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout these Technical Specifications. THERMAL POWER 1.2 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. RATED THERMAL POWER 1.3 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 600 MWt. OPERATIONAL MODE 1.4 An OPERATIONAL MODE shall correspond to any one inclusive en'bina-tion of core reactivity condition. >ower level and average reactor coolant temperature specified in Tasle 1.1. ACTION 1.5 ACTION shall be those additional requirements specified as corollary statements to each principle specification and shall be part of the specifications. OPERABLE - OPERABILITY 1.6 A system, subsystem, train, compnent or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, electric power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform itsfunction(s)arealsocapableofperformingtheirrelatedsupport function (s). YANKEE-ROWE 11
. . . ~ ~ . _ ..... , _. __ _ , 4. . . .
' OEFINITIONS I
rep 0RTABLE EVENT 1.7 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR part 50. CONTAINMENT INTEGRITY g l 1.3 CONTAINMENT INTEGRITY shall exist when: 1.8.1 All penetrations required to be closed during accident conditions are either:
- a. Capable of being closed by an OPERA 8LE containment automatic isolation valve system, or
- b. Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-1 of Specification 3.6.2.
1.8.2 All equipment hatches are closed and sealed, 1.8.3 The air lock is OPERABLE pursuant to specification 3.6.1.3, and 1.8.4 The containment leakage rates are within the Ilmits of Specification 3.6.1.2. CHANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated. CHANNEL CHECK 1.10 A CHANNEL CHECK shall be the qualitative assessment of channel , behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument, channels measuring the same parameter, t YANKEE-MWE 1-2 Amendment No.104 ..._..._._. _ _ _ 1 r ,__ _ y. y _ .. 1.__.y_...y__.._,_._, _. .
i l INSTRUMENTATION FIRE DETECTION INSTRUMENTATION
- t,tMITING CONDITION FOR OPERATION 3.3.3.4 As a 'cinimum, the fire detection instrumentation for each fire l detection zone shown in Table 3.3.6 shall be OPERA 8LE.
APPt.!CABILITY_: Whenever equipment in that fire detection zone is required to be OPEAA6LE. , ACTION _: l With the number of OPERABLE fire detection instruments'less than required by Table 3.3.6: ,
- s. Within 1 hour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, and
- b. Restore the inoperable instrumenth) to OPERABLE status within 14 days or prepare and submit a speciel Report to the Co mission pursuant to Speciffeation 6.9.6 within the next 30 days out.
linin 9 the action taken, the cause of the inoperabilit the plans and schedule for restoring the instrument (s)y to and CPERABLE status,
- c. The :rovisions of Specificatiens 3.0.3 and 3.0.4 are not applicable.
SURVEll. LANCE R!OUt#!9ENTS 4.3.3.4 Each of the'above retuired fire detection instruments shall be degnstrated 07EAA5LE at least once per 6 months by performance of a C hi.iEL FUNcit NAL TEST. Amtnd ant No. .pf.194 YANXEE.A0W( 3/4 3 27 t ! 6 m-..__=_____
INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT INSTRUMENTAff0N LIMITING CON 0! TION FOR OPERATION 3.3.3.6 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-8 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not onceeded. The alarm / trip setpoints of these channels shall be determined in acgordance with the Off-Site Oose Calculation Manual (00CM). APPt tC AntttTY As shown in Table 3 3-8. f ACTION:
- a. With a radioactive liquid effluent monitoring instrumentation
- channel alarm / trip setpoint less conservative than a value which t
will ensure that the limits of Specification 3.11.1.1 are met, without delay, take actions to suspend the release of radioactive l Itquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is I acceptably conservative.
- b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-8. Enert reasonable efforts to return the instrument (s) to OPERABLE status within 30 days and if unsuccessful explain in the next Semiannual Radioactive Effluent Release Report the reason fo* delay in correcting the inoperability,
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVE!LLANCE REQUIREMENTS 4.3.3.6 Each radioactive Itquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, WNNEL CALIBRAT!ON, and CHANNEt. FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3 6. YANREE ROWE 3/4 3-32 AMENDMENT No. Ad, pf.104
f . . , I
; INST'RUMENTATION RADI0 ACTIVE GASEOUS EFFLUEN'T MON!TORING INSTRUMENTATION ;
i ! LIMITING CON 0! TION FOR OPERATION t lt
' 3.3.3.7 The radioactive gaseous effluent monitoring instrumentation i l
channels shown in Table 3.3-9 shall be OPERABLE with their alarm setpoints j set to ensure that the limits of specification 3.11.2.1 are not exceeded, i The alarm setpoints of these channels shall be determined in accordance ij liwiththe00CM. APPLICABILITY: As shown in Table 3.3-9. ?
; ACTION:
l , a. With a radioactive gaseous effluent monitoring instrumentation ,
- channel alarm setpoint less conservative than a value which will t
ensure that the limits of Specification 3.11.2.1 are met, without j delay, take actions to suspend the release of radicactive gaseous : i effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably ; l conservative. ;
- b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERA 8LE, take the ACTION shown in Table 3.3-9. Exert reasonable efforts to return the instrument (s) to OPERABLE status within 30 days and if ,
unsuccessful explain in the next Semiannual Radioactive Effluent Release Report the reason for the delay in correcting the ! inoperability. 1
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
I SURVE!LLANCE REQUIREMENTS 4.3.3.7 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERA 8LE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations during the M00E5 and at the frequencies shown in Table 4.3-7. > I i-l YANKEE-R0WE 3/4 3-37 Amendment No.,5f.104 ( l
r i MAIN CCOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CON 0! TION FOR OPERATION 3.4.7 The specific activity of the primary coolant shall be Itmited to:
- a. s 1.0 uti/ gram DOSE EQUIVALENT I-131, and <
b, s 100/E vCi/ gram. . . APPLICABILITY: MODES 1, 2, 3, 4 and 5 ACTION: MODES 1, 2 and 3*
- a. With the specific activity of the primary coolant >.1.0 uct/ gram 00SE EQUIVALENT I-131 but within the allowable Itmit (below and to the lef t of the line) shown on Figure 3.4-1, operation may continue for up to 48 hours provided that operation under these circumstances shall not exceed 10 percent of the unit's total yearly operating time. The provisions of Specification 3.0.4 are not applic.ble,
- b. With the specific activity of the primary coolant > 1.0 9C1/ gram DOSE EQUIVALENT I-131 for more than 48 hours during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at least HOT STANOBY with T,yg < 514*F within 6 hours.
- c. With the specific activity of the primary coolant >> 100/E uC1/ gram, be in at least HOT STANOBY with T,yg < 514*F within 6 hours.
MODES 1, 2, 3, 4 and 5
- a. With the specific activity of the primary coolant > 1.0 9C1/ gram DOSE EQUIVALENT I-131 or > 100/E 9Ct/ gram, perform the sampling and analysis requirements of item 4a of Table 4.4-2 until the specific activity of the primary coolant is restored to within its 11mits.
9
*With T,yg a 514'F.
YANK!E-ROWE 3/4 4-15 Amendment No.104
_. . . . . _ ~ _ _ . 4 I MAIN COOLANT SYSTEM
' I SURVEILLANCE REQUIREMENTS I,
4.4.7 The specific activity of the primary coolant shall be determined to -
- , l be within the limits by performance of the sampling and analysis program of
's Table 4.4-2.
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'M AIN C00 TANT SYSTDi STRUCTURAL INTEGRITY AS3E CODE CLASS 1, 2. and 3 CQ4PONENTS LIMITING CONDITION FOR OPEFATION 3.4.9 The structural integrity of ASME Code Class 1, 2, and 3 components (except steam generator tubes) shall be maintained in accordance with Specifications 4.4.9.1, 4.4.9.2, and 4.4.9.3.
APPLICABILITY: ALL MODES ACTION:
- a. With the structural integrity of any ASME Code Class 1 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 500F above the.
minimum temperature required by NDT considerations,
- b. With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected ccuponent(s) to within its
. limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 2000F.
- c. With the structural integrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its licit or isolate the affected component (s) frem service.
- d. The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REOUIRDiENTS 4.4.9.1 The inspection program delineated in Specification 4.0.5 shall be performed. If not applicable to 10 CFR 50.73, an initial report of any l abnormal degradation of the structural integrity of the Safety Class 1 components detected during the above required inspections shall be made within 10 days after detection and the detailed report shall be submitted pursuant to Specification 6.9.6 within 90 days after completion of the surveillance requirements l of this specification. i
. 1 YANKEE ROWE 3/4 4-26 Amendment No. 8 ( 104 l
g ' O I . r ) MAIN COOLANT SYSTEM l SURVEILLANCE REQUIREMENTS (Continued) l 4.4.10.4 Acceptance Criteria 4
- a. As used in this Specification:
I
- 1. Imperfection means an exception to the dimensions ,
i finish or contour of a tube from that required by fabri-
- cation drawings or specifications. Eddya
- urrent testing
! indications below 20% of the nominal tube wall thickness , j if detectable, may be considered as imperfections. I 2. Degradation means a service-induced cracking, wastage, i wear or general corrosion occurring on either inside or ! outside of a tube, i 1 3. Degraded Tube means a tube containing imperfections j , t 207 of the nominal wall thickness caused by degradation. 4 l 4. % Degradation means the percentage of the tube wall thickness affected or renoved by degradation. i i
- 5. Defect means an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective.
l 6. Plugging Limit means the imperfection depth at or beyond I which the tube shall be renoved from service because it j may become unserviceable prior to the next inspection and 1 is equal to (40)% of the nominal tube wall thickness.
- 7. Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its i
structural integrity in the event of a loss-of-coolant i accident or a steam line or feedwater line break as
! specified in 4.4.10.3.c , above.
t i
- 8. Tube Inspection means an inspection of the steam generator
- tube from the point of entry (hot leg side). past the top I (fifth) support and, where practical, completely around the U-bend to the top support of the cold leg.
, b. The steam generator shall be determined OPERABLE after com- ; pleting the corresponding actions (plug all tubes exceeding l
the plugging limit and all tubes containing through wall cracks) required by Table 4.4-5. l YANKEEJt0WE 3/4 4-35 Amendment No. 54 ; 2
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l J 1 1 f MAIN COOLANT SYSTEM l SURVEILLANCE RIQUIREMENTS (Continued) l l 4.4.10.5 Reports I
- a. Following each inservice inspection of steam generator tubes, i
the number of tubes plugged in each steam generator shall be reported to the Comission within 15 days. i' b. The complete results of the steam gen'erator tube inservice inspection shall be submitted to the Comission in a Special Report pursuant to Specification 6.9.6 within 12 months following - the completion of the inspection. This Special Report shall . include: l
- 1. Number and extent of tubes inspected. 4
- 2. Location and percer.t of wall-thickness penetration for l
each indication of an imperfection.
- 3. Identification of tubes plugged.
Results of steam generator tube inspections which fall into 4 c. l Category C-3 and require immediate notification of the Commission I pursuant to 10 CFR 50.72 shall be reported prior to resgmotion of plant operation. The written followup of this report l pursuant to . 10 CFR 50.73 shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrenca. , 1 i l 4 0 l l 5 h 3/4 4-36 Amendment No. [ 104 YANKEE-ROWE i
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R . . n, s= TABLE 4.4 -4 E m MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION i
! Preservice Inspection i No No. of Steam Generators per Unit Four i: First inservice Inspection 4..
All Ej Second & Subsequent inservice Inspections' I One g-Table Notation: 1. ,f The inservice inspection may be Ilmited to one steam generator ca a rotating schedule .1 encompassing 3 N % of the tubes (where N is the number of steam generators in the plant) - .}* if the are results ofinthe performing first a like or previous inspections indicate that all steam generators manner. Note that under some circumstances , the opera ting 3E conditions in one in other steam or more steam generators may be found to be more severe than those generators. -{ El to inspect the most severe conditions.Under such circumstances the sample sequence shall be modified ~j 52
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TABLE 4.4-5 I Y STEAN GENERATOR TUBE INSPECTION q R
- lll f 1st SAMPLE INSPECTION 2nd SAMPLE INSPECTION 3rd SAMPLE INSPECTION Sample Size Result Action Required Result Action Required Result Action Required A minimum of C-1 None N/A N/A N/A . N/A S Tubes per S.G.
C-2 Plug defective tubes C-1 None N/A N/A and inspect additional
- 2S tubes in this S.G. C-2 Plug defectiv& tubes C-1 None 1 and inspect additional C-2 Plug defective tubes
- I, 4S tubes in this S.G. Perform action for C-3 C-3 result of first ,
sample i w , Perfora action for . 3 C-3 C-3 result of first N/A N/A
, sample
,I 4 C-3 Inspect all tubes in All other
" this S.G., plug de- S.C.s are None N/A N/A factive tubes and C-1 inspect 2S tubes in Soue S.G.s Perform action for N/A N/A sach other S.G. C-2 but no C-2 result of second
!] additional sample' Ij Notification . S.G. are !i to NRC pursuant to C-3 10 CFR 50.72(b)(2)(i) Additional Inspect all' tubes in p 'and 10 CFR 50.73(a)(2) S.G. is C-3 each S.G. and plug d (ii) , defective tubes. N/A N/A E. Notification to N NRC pursuant to < E, 10 CFR 50.72(b)(2)(i) z o and 10 CFR 50.73(a)(2)(ii)
- N
, 3 ,3 p here N is the number of steam generators in the unit, and n is the number of steam generators ,,i Jaspected during an inspection.
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EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS LIMITING CONDITION FOR OPERATION 3.5.2 The ECCS subsystems shall be OPERABLE with:
- a. Three OPERABLE independent ECCS safety injection subsystems with each subsystem comprised of:
- 1. One OPERABLE high pressure safety injection pump,
- 2. One OPERABLE low pressure safety injection pump, .
- 3. An OPERABLE flow path capable of taking suction from the safety injection tank on a safety injection ,
signal .
- b. An OPERABLE ECCS recirculation subsystem with an OPERABLE flow path capable of taking suction from the containment sump and recirculating to the safety injection header.
- c. An OPERABLE ECCS long term hot leg injection subsystem with an OPERABLE flow path capable of taking suction from the ECCS safety injection subsystem and discharging to the Main Coolant System #4 hot leg.
APPLICABILITY: K) DES 1, 2, 3, 4* and 5* ACTION!
- a. With one ECCS safety injection subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours or be in at least HOT SHUTDOWN with Main Coolant pressure < 1000 psig within the next 12 hours.
- b. The provisions of Specification 3.0.3 are not applicable.
l
- Main coolant pressure L1000 psig.
YANKEE-ROWE 3/45-3 Amendment No. 32,104 i i - 2-
- . - .. . = - - _ , , - . . .
_ ---~ ~ -
, . . ', - l l EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS LIMITING CONDITIOS FOR OPERATION 3.5.3 T'he ECCS subsystems shall be OPERABLE with:
l a.* As a minimum, one OPERABLE ECCS safety injection subsystem l
' c'emprised of the following:
- 1. One OPERABLE high pressure safety injection pump,# l
- 2. One OPERABLE low pressure safety injection pump, and l An OPERABLE flow path" capable of taking suction from j 3.
the safety injection tank. b* An OPERABLE ECCS recirculation subsystem with an OPERABLE flow l I path capable of taking suction from the contagment sump and < recirculating to the safety injection header. j c.* An OPERABLE ECCS long term hot leg injection subsystem with an l OPERABLE flow path capable of taking suction from the ECCS safety injection subsygem and discharging to the Main Coolant ' System loop 4 hot leg i APPLICABILITY: MODE 4 and 5. l l
- Main coolant pressure < 1000 psig but > 300 psig. ,
#A maximum of one HPSI pump and one LPSI pump shall be OPERABLE whenever
' MCS temperature is between 200*F and 324*F. All HPSI pumps and LPSI pumps shall be inoperable whenever MCS temperature is < 200*F, except that:
, a. One LPSI pump may be energized for surveillance testing require-ments or for mixing the safety ir.jection tank provided that either:
- 1. The reactor vessel head is removed, or
- 2. The LPSI pump recirculation valve (s) are open to limit pump discharge pressure to < 280 psig.
- b. Two HPSI pumps may be energized Tor surveillance testing requirements provided that either:
i
- 1. The reactor vessel head is removed, or
- 2. At least one pressurizer code safety valve is removed.
NWhenever the MCS temperature is < 324*F, the reactor vessel head is bolted on and both pressurizer code safety valves are installed, all
- four loop injection MOV's and all four LPSI MOV's shall be closed and I the LPSI pump recirculation valve shall be open, except that loop SI system header isolation valves to the MCS cold legs may be open provided 4
that the associated MCS loop isolation valves are closed or when required 7 to be open to perfom Surveillance Requirements 4.5.2.a.1, 4.5.2.e.3(a) and 4.5.2.f.
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YANKEE-ROWE 3/4 5-9 Amendment No. O, 52,59 SEP 141979
.--_ ~- - _ ~. - - . . - ~T . :-- - r: r :z m :- -.
EMERGENCY CORE COOLING SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) ACTION:
- a. With the ECCS safety injection subsystem, the recirculation subsystem, or the long term hot leg injection subsystem inoperable,* restore all subsystems to OPERABLE status within 1 hour or reduce main coolant pressure to < 300 psig within the next 20 hours.
- b. With more than one HPSI pump and/or one LPSI pump OPERABLE and MCS temperature between 200*F and 324*F, de-energize all except one HPSI and one LPSI pump within one hour by opening and locking the associated power supply breakers in the racked-out position or removing the associated power supply breaker from the cubicle.
- c. With any HPSI or LPSI pump OPERABLE and MCS temperature s 200*F, unless the exception conditions are satisfied, de-energize all HPSI and LPSI pumps within one hour by opening and locking the associated power supply breakers in the racked-out position or removing the associated power supply breaker from the cubicle.
- d. With any loop injection MOV or LPSI MOV or with the LPSI pump recirculation valve closed, and MCS temperature is s 324*F, the reactor, vessel head is bolted on and both pressurizer code safety valves are installed, restore each valve to its required position within one hour.
- Main Coolant Pressure < 1000 psig but 2 300 psig 0
l l YANKEE-ROWS 3/4 5-10 Amendment No. JdI,104 l
- .~.= - - , . . _ _ _ . . _ . . - _ _ _ _ , . _ . , _ , . . . _ , , _ . ,. ._ _ , , _
t CONTAIMMENT SYSTEMS ,, CONTAINMENT VESSEL STRUCTURAL INTEGRITY , LIMITING CONDITION FOR OPERATION -- 3.6.1.6 The structural integrity of the containment vessel shall be maintairjed at a level consistent with the acceptance criteria in Specification 4.6.1.6. , APPLICABILITY: MODES 1. 2. 3 and 4. ACTION: With the structural integrity of the containment vessel not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Main Coolant System temperature above 200*F. SURVEILLANCE REQUIREMENTS 4.6.1.6 The structural integrity of the containment vessel shall be detennined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of the accessible interior and exterior surfaces of the vessel and verifying no apparent changes in appearance of the surfaces or other abnormal i degradation. If not applicable to 10 CFR 50.73, an initial report of I any abnormal degradation of the containment vessel detected during the above required inspections shall be made within 10 days after detection and the detailed report shall be submitted to the Comission pursuant to
' Specification 6.9.6 within 90 days after completion of the surveillance requirements of thts specification. l j
j , p YA:::*EE-RCiE 3/4 6-7 , Amendmerit No. ,W,104 8 i l 1
- . . . . . . - - _ ~ . _ ~ _ . - - _ - , . - _ . .-,--.._%.. . , . ~ _ . . _-...
Lv'.: A NM-Ni sis 1 EMS CONTINUOUS LEAK MONITORING SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.7 The continuous leak monitoring system shall be OPERABLE within 12 hours following establishment of CONTAINMENT INTEGRITY with:
- a. Containment internal pressure greater than or equal to 0.75 psig, ~
- b. At least fourteen containment temperature detectors, l
- c. At least.one containment pressure detector, and
- d. Two relative humidity detectors and/or dew probes.
APPLICABILITY: Modes 1, 2, 3 and 4 ACTION: With the continuous leak monitoring system inoperable, restore the system to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REOUIREMENTS 4.6.1.7 The continuous leak monitoring system shall be demonstrated OPERABLE by:
- a. Verifying containment internal pressure to be greater
. than or equal to 0.75 psig at least once per 12 hours.
3
- b. Calibrating the temperature channels, the pressure channels, the dew point channels or the relative humidity channels at least once per 18 months.
\
YANKEE-RDWE 3/4 6-8 Amendment No. 49,86 N' "" e -** ., =4 +4.* m w% . , 6-- *' N * '
PLANT SYSTEMS 3/4'.7.10FIFISUPPRESSIOhSYSTEMS
~
g FIRE SUPPRESSION WATER' SYSTEM
~
LIMITING C05DITION FOR OPERATION 3.7.10.1 The fire suppression water system shall be OPIRAELE with:
- a. Two motor operated high pr, essure pumps, each with a capacity of 1000 gym, with their' discharge aligned to the fire sup-pression header
- and
- b. A diesel engine driven pu=p with a capacity of' 2000 gym, with its discharge aligned to the fire suppression header and
- c. . An OPERABLE flow path with the diesel engine driven pump capable of taking suction from the fire water storage tank and the motor operated pu=ps capable of taking suction from Sherman Pond and transferring the water through distribut' ion piping with OPERABLE sectionalizing centrol or isolation valves to the yard hydrant curb valves. .
APPLICABILITY: , At all times. ACTION: . ( .
- a. With one pump and/or one water supply inoperative, restore equipuent to OPERABLE status within. 7 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.6 within the next 30 days outlining the plans and procedures to be used to provide for the loss of redundancy in this system. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
- b. With the fire suppression water system otherwise inoperable:
- 1. Establish a backup fire suppression water system within 24 hours, and
- 2. Submit a Special Report in accordance with Specification 6.9.6; a) By telephone within 24 hours, b) Confirmed by telegraph, mailgram or facsimile transmission no later than the first working day following the event, and 3/4 7-30 Amendment No.j#, g,104 YANKEE-ROWE 6
~"*** N N eue=***-e* *%,
PLANT SYS T.S , . , , SPRAY AND SPRINII.IR SYSTIMS LIMITING CONDITION FOR OPERATION 3.7.10.2 The following sprinkler systems shall be CPIRABLI:
- a. Cable Tray House sprinkler system.
- b. Turbine Building:
, 1. Zone 1 sprinkler system -
- 2. Zone 2 sprinkler system
- 3. Zone 3 sprinkler spstem
- 4. Transformer oil cooler deluge system 5 ., Turbine building columns spray system.
- c. Emergency Diesel Generator Cubicles ,
. d. Auxiliary Boiler Room Ao?LICA3IIITY: k'henever equipment in the sprinkler protected areas is re-quired to be CPIRA3LI: .
ACTION: .
- a. With one or more of the abcVe required sprinkler systems inoperable, establich a continuous fire watch with backup fire suppression equipment for the unprotected area within
- 1 hour; restore the system to OPERABLE status within 14 days ~
or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.6 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
- b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
SURVIIIIANCE RIQUIRIMINTS - 4.7.10.2 Each of the above required sprinkler systems shall be demonstrated OPERA 3LI:
- a. At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.
YA'.",:II-Rok /. 3/4 7-33 (cendment No. AT, M ,fif, 104 . . . , - . .......__......i - .. . . . . . . . . _ _ _ _ . . . , , _ . . . _ _ . . , . . . ,
- e. . . .
lPLANT SYSTEMS HIGH PRESSURE CO3 SYSTEM LIMITING CONDITIONS FOR OPERATION 3.7.10.3 The high pressure CO2 system located in Manhole No. 3 shall be OPERABLE with at least 90% of full charge weight in the main and auxiliary CO2 cylinders. APPLICABILITY: Whenever equipment in the high pressure CO2 protected area is required to be OPERABLE. Exception: Automatic initiation of the high, pressure CO2 system may be disabled to allow maintenance activities within Manhole No. 3 providing a continuous fire watch is established and the high pressure CO2 system remains capable of being manually initiated. ACTION:
- a. With the abcve required high pressure CO2 system inoperable, establish a continuous fire watch with backup fire suppression equipment for the unprotected area within 1 hour; restore the system to OPERABLE status within 14 days or. Prepar'e and submit a Special Report l
\
to the Commission pursuant co Specification 6.9.6 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status,
- b. The provisions of Specifications 3.0.3 tnd 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.7.10.3 The above required high pressure CO2 systems shall be demonstrated - OPERABLE:
- a. At least once per 6 months by verifying CO2 cylinder weight,
- b. At least once per 18 months by:
- 1. Verifying the system valves actuate automatically.
- 2. Performance of a flow test through headers and nozzles to I assure no blockage. I O
O 3/4 7-35 Amendment No. #6. 47, 56, 5d.% 104
, YANKEE ROWE
^ - ,
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=. . - - = . -
. ~ - - . . . , . - - . _ . - ~ . ~ . . - - . - . - ~ . . - . - .
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PLANT SYSTEMS HALON SYSTEMS i . LIMITING CONDITION FON 0PERATION 3.7.10.5 The followihg Halen systems shall be OPERA 3LE with the storage tanks having at least 95% of full charge weight and 90% of full charge pressure. 7
- a. Switchgear Room
- b. Battery Room No. I
- c. Battery Room No. 2 APPLICABILITY: Whenever equipment in the Halon protected areas is required to 1 be OPERA 3LE.
ACTION:
- a. With one or more of the above required Halon systems inoperable, establish an hourly fire watch patrol with backup fire suppres-sion equipment for the unprotected area (s) within 1 hour; re-store the system to OPERABLE status within 14 day.s or prepare and submit a Special Report to the Commission pursuant to l Specification 6.9.6 within the next 30 days outlining the action taken,. the cause of the inoperability and the plans and schedule
,l for restoring the system to CPERA3LE status.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not .
! applicable.
1 , SURVEILLANCE REQUIREMENTS 4.7.10.5 Each of the above required Halon systems shall be demonstrated OPERABLE: .
- a. At least once per 6 months by verifying Halon storage tank weight and' pressure.
- b. At least once per 1S months by:
- 1. Verifying' the system, including associated ventilation dampers and fire door release mechanisms, actuates man-1 ually and automatically, upon receipt of a simulated actuation signal, and
- 2. Performance of a flow test through headers and noz:les 1
to assure no blockage. 3/4 7-38 5mendmentNo..pdI,104 , YANKEE-ROWE P D h e i J . . _ _ . . __ __ _ _
l i PLA.'T N SYSTEMS 70A}! SYSTEMS LIMITING CONDITION FOR OPERATION The following foam syst s shall be OPERABLI: 3.7.10.6 , Turbine Lube Oil Reservoir. Ap?LICA31LITY: Whenever the turbine lube oil reservoir is required to be OPERABLE. i~ ACTION:
- a. With the above required foam system inoperable, establish a continuous fire watch with backup fire suppression equipment for the unprotected area within I hour; restore the, system to OPERA 3EI status within 14 days or prepare and submit'a -
t l Special Report-to the Commission pursuant to Specification:- 4 6.9.6 within the next 30 days outlining the action taken, the
- cause of the inoperability and the plans and schedule for restoring the system to OPERA 3LI status.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not l
applicable. 3 i SURVIILLGCI RIQUTRIMINTS a 4.7.10.6 The above required foam system shall be denonstrated OPERA 3LI:
- a. At least once per 12 months by cycling each testable valve in the flow path through at least one complete eycle of full travel and verifying the foam tank is. *
- full.
1 I b. At least one per 18 months by: .
- 1. Cycling each valve in the flow path that is not testable during plant operation through at least ene complete cycle of full travel.
- 2. A visual inspection of the foam header to verify integrity, and
- 3. A visual inspection of each foam nozzle area to verify that the spray pattern is not obstructed.
- c. At least once per 3 years by performing an air flow test through the foam header and verifying each faam nozzle is i
unobstructed. l 4 1As:.22 Rcut 3,. 7 3, f;. . i uo.;,<; ,07
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'* 3/4.11 RADIOACTIVE EFFLUENTS i
i 3/4.11.1 LIQUID EFFLUENTS I
'! CONCENTRATION LIMITING CONDITION FOR OPERATION
!3.11.1.1 The concentration of radioactive material released from the site I (see Figure 5.1-4) shall be limited to the concentrations specified in 10
' CFR Part 20, Appendix 8, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10 6 microcuries/mi total activity.
APPLICABILITY: At all times. l ACTION: With the concentration of radioactive material released from the site exceeding the above limits, without delay, take actions to restore the concentration to within the above limits. l SURVEILLANCE REQUIREMENTS 1 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1. 4.11.1.1.2 The results of radioactive analysis shall be used in accordance with the methods of the 00CM to assure that concentrations at the point of release are maintained within the limits of Specification 3.11.1.1. 1 i YANKEE-ROWE 3/4 11-1 Amendment No.jp6",104
._ -. _ -.. . . . . - . - ~ . . - . . - . . . . - . - - . - . - . - - - . . . . . . . . - - - . . . ..
ij RADIOACTIVE EFFLUENTS i .
' ., DOSE, (LIQUID)
; LIMITING CONDITION FOR OPERATION
;i --
3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the site (see i { Figure 5.1-4) to available uptake pathways shall be limited: I
- a. During any calendar quarter: less than or equal to 1.5 m'em r to the total body and to less than or equal to 5 meca to any organ, and
- b. During any calendar year: less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
APPLICABILITY: At all times. ACTION:
- a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, and if not applicable to 10 CFR 50.73, prepare and submit to the l Commission within 30 days, pursuant to Specification 6.9.6, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be within the above limits.
I' b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculations - Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM at least once per 31 days. YANKEE-ROWE 3/4 11-4 Amendment No.,fd5104
RADI0 ACTIVE EFFLUENTS i LIQUID RA0 WASTE TREATMENT l LIMITING CONDITION FOR OPERATION i I 3.11.1.3 The liquid radwaste treatment system shall be used to reduce the radioactive materials in the liquid wa:te prior to its discharge when the
' estimated doses due to the liquid effluent from the site (see Figure 5.1-4) when averaged over 31 days, would exceed 0.06 mrem to the total body, or l.
0.2 mrem to any organ. . APPLICABILITY: At all times. ACTION:
- a. With liquid waste being discharged without processing through appropriate treatment systems as defined in:the 00CM and estimated doses in excess of the above limitsg and,1f not applicable to 10 CFR 50.73, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.6,.a Special Report which includes the following information:
- 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reasons for the inoperability,
- 2. Action (s) taken to restore the inoperable equipment to operable status, and
- 3. Summary description of action (s) taken to prevent a recurrence,
- b. The provisions of Specification 3.0.3 and 3.0.4 are not appitcable.
SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases shall be estimated at least once per 31 days, in accordance with the 00CM. No dose estimates are required if the liquid radwaste treatment system has been continually used to reduce the radioactive materials in liquid waste prior to its discharge, or if no liquid discharges have taken place over the appropriate 31 day period. YANKEE-ROWE 3/4 11-5 AmendmentNO.,fd5104 4
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-n._, _ _ , _ _ _ _ _ _ _ . _ __ _ _
RADIOACTIVE EFFLUENTS LIQUID HOLDUP TANKS. LIMITING'CONDITICN FOR OPERATION 5 s
' 3.11.1.4 The quantity of radioactive material contained in any outside temporary tanka shall be limited to less than or equal to 10 curies, i
excluding tritium and dissolved'or entrained noble gases. 1 APPLICABILITY: At all times. ACTION:
- a. With the quantity of radioactive material in any outside temporary tank exceeding the above limit, without delay, take action to suspend all additions of radioactive material to the tank. Within 48 hours reduce the tank contents to within the
' limit and describe the events leading to this condition in the l next Semiannual Radioactive Effluent Release Reporte l
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.
- NOTE: Tanks included in this Specification are those temporary outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents, or that do not have tank overflows connected to the liquid radwaste treatment system.
Amendment No. 104 YANKEE-ROWE 3/4 11-6
RADI0 ACTIVE EFFLUENTS l j 3/4.11.2 GASECUS EFFLUENTS DOSE RATE I l LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see l Figure 5.1-3) shall'be limited to the following: i i a. For noble gases: less than or equal to 500 mrem /yr to the total body and less than or equal to 3,000 mrem /yr to the skin,- and I b. For iodine-131, tritium, and radionuclides in particulate form with half lives greater than 8 days: less than or equal to 1500 mrem /yr to any organ, f APPLICABILITY: At all times"
- I ACTION:
With the dose rate (s) exceeding the above limits, without delay, take actions to decrease the release rate to within the above limit (s). I SURVEILLANCE REQUIREMENTS l l 4.11.2.1.1 The dose rate due to noble gases in gaseous e#fluents shall be determined to be within the above limits in accordance with the methods and ' procedures of the 00CM. 4.11.2.1.2 The does rate due to Iodine-131, tritium, and radionuclides in I particulate form with half lives greater than 8 days, in gaseous effluents shall be determined to be within the above limits in accordance with the 1 methods and procedures of the 00CM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 4.11-2. l l 1 YANKEE-ROWE 3/4 11-7 Amendment No. 104 1 _ . _ _ . - _ _ _ _ _ _ _ _ . _ _ _ _ . . _ . _ . . _ . . . _ . . .....t.., , . _ _ . _ .
I
! RADI0 ACTIVE EFFLUENTS l DOSE, NOBLE GASES t
LIMITING CONDITION FOR OPERATION i. e j - 3.11.2.2 The air dose due to noble gases released in gaseous effluents t . from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) l' shall be limited to the following: I a. During any calendar quarter: less than or equal to 5 mrad for
!' gamma radiation and less than or equal to 10 mrad for beta
' radiation and, i b. During any calendar year: less than or equal to 10 mrad for j gamma radiation, and less than or equal to 20 mrad for beta jj radiation.
I! APPLICABILITY: At all times. I
! ACTION:
i
!' a. With the calculated air dose from radioactive noble gases in ,
gaseous effluents exceeding any of the above limits and if not l l applicable to 10 CFR 50.73, prepare and submit to the Commission I' within 30 days, pursuant to Specification 6.9.6, a Special Report j which identifies the cause(s) for exceeding the limit (s) and i defines the corrective actions to be taken to reduce the releases and the proposed corrective actions to be taken to assure that i-subsequent releases will be within the above limits.
- b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
i SURVEILLANCE REQUIREMENTS 4.11.2.2 Dose Calculation: Cumuiative dose contrioutions for current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once every 31 days. YANKEE-ROWE 3/4 11-10 Amendment No. 104
I. RADIOACTIVE EFFLUENTS DOSE: IODINE-131, TRITIUM, AND RADIONUCLICES IN PARTICULATE FORM l LIMITING CONDITION FOR OPERATION
! 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodi.ne-131, tritium, and
! radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:
I
- a. During any calendar quarter: less than or equal to 7.5 mrem to l
any organ and, I
! b. During any calendar year: less than or equal to 15 mrem to any organ APPLICABILITY: At all times.
i ACTION: I i
! a. With the calculated dose from the release of radiciodines,
! radioactive materials in particulate form, or radionuclides other I than noble gases ir gaseous effluents exceeding any of the above limits and if not applicable to 10 CFR 50.73, prepare and submit l to the Commission vi+.hin 30 days, pursuant to Specification 6.9.6, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be within the above limits.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not l
applicable. t
\
t SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations: Cumalative dose contributions for th'e current calendar quarter and current calecdar year for iodine-131, tritium, and . radionuclides in particulate form with half-lives greater than 8 days shall 1 be determined in accordance with the 00CM at least once every 31 days. ( i l l Amendment No. 104 YANKEE-ROWE 3/4 11-11 1
; i RADI0 ACTIVE EFFLUENTS i GASEOUS RADWASTE TREATMENT
! LIMITING CONDITION FOR OPERATION l
l' 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXH TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous I waste prior to their discharge when the estimated gaseous effluent air doses due to gaseous effluent releases from the site to areas at and beyond
! the SITE BOUNDARY (see Figure 5.1-3) would exceed 0.2 mrad for gamma radiation and 0.4 ' mrad for beta radiation over 31 days. The VENTILATION EXHAUST TREATMENT. SYSTEM shall be used to reduce radioactive materials in gaseous waste prior.to their discharge when the estimated doses due to gaseous effluent releases from the site to areas at and beyond the SITE I BOUNDARY (see . Figure 5.1-3) would exceed 0.3 mrem to any organ over 31 days.
APPLICABILITY: At all times. ACTION: ,
- a. With gaseous waste being discharged without processing through appropriate treatment systems as defined in the 00CM and in excess of the above limits and if not applicable to 10 CFR 50.73, l prepare and submit to the Commission within 30 days, pursuant to l Specification 6.9.6, a Special Report that includes the following information:
- 1. Explanation of why gaseous radwaste was being discharged
! without treatment, identification of any inoperable equipment or subsystems, and the reasons for the inoperability,
- 2. Action (s) taken to restore any inoperable equipment to operable status, and
- 3. Summary description of action (s) taken to prevent a recurrence.
I
- b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.4 Doses due to gaseous releases from the site shall be estimated at least once per 31 days, in accordance with the ODCM. i YANKEE-RDWE 3/4 11-12 Amendment No.jpd$104
-__= - .- _ - .
I RADI0 ACTIVE EFFLUENTS
! EXPLOSIVE GAS MIXTURE i
LIMITING CONDITION FOR OPERATION
. l l!
3.11.2.5 The concentration of oxygen in the waste gas holdup system shall l be limited to less than or equal to 2% by volume. < 6 l APPLICABILITY: At all times. ACTICA: ,
- a. With the concentration of oxygen in the waste gas holdup system greater than 2% by volume but less than or equal to 4% by volume, restore the concentration of oxygen to within the limit within 48 hours,
- b. With the concentration of oxygen in the waste gas holdup system greater than 4% by volume, without delay, take actions to suspend l all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 2% within 48 ;
hours, or reduce the hydrogen concentration to less than 44 by I volume. I 4 i
- c. The provisions of Specifications 3.0,3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS ' 4.11.2.6 The concentrations of oxygen in the waste gas holdup system shall be determined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the oxygen monitor required OPERABLE by Table 3.3-9 of Specifications 3.3.3.7. f YANKEE-ROWE 3/4 11-13 Amendment No.fAdi104
/
1 RADI0 ACTIVE ETTLUENTS CAS STORACE TANK . LIMITING CONDITION TOR OPERATION 3.11.2.6 The quantity of radioactivity concained in the vaste saa surge drum
- sh'all be limited to less than or equal to 7.0E+04 curies noble gases '
(considered as Ie-133). APPLICABILITY: At all times. ACTION:
- a. With the quantity of radioactive material in the waste gas surge drum exceeding the above limit, without delay take actions to suspend all additions of radioactive material to the drum and within 48 hours either reduce the drum's contents to within the limit or provide l
immediate notification to the Commission pursuant to 10 CFR 50.72(b)(2). The vritten follovup report required pursuint to 10 CFR 50.73 i shall include a description of activities planned and/or taken to reduce
! the drums contents to within the above limit.
- b. The provisions of Specificatione-3.0.3 and 3.0.4 are not applicable.
) SURVEILLANCE REQUIREMENTS 4.11.'.6 2 The quantity of radioactive material contained in the vaste gas surge drum shall be determined to be less than or equal to 20% of the above limit at least once per (30 days). If the quantity of radioactive material contained in the waste gas surge drum exceeds 20% of the above limit, or the specific activity of the primary coolant exceeds the limits of Specification 3.4.7, surveillance vill be performed at least once per 24 hours.
- For the purpose of determining the quantity of radioactive gases, the vaste gas surge drum (TK-31) volume shall include the associated vaste cover gas systes volume and be considered equivalent to 30,000 cubic feet at STF.
Amendment No1 D YANKIE-ROVE 3/4 11-14
* -"-- - e. s...ep e o ,+ , .%., ,,m _ , , , ,_
i RAOI0 ACTIVE EFFLUENTS l i 3/4.11.3 SOLIO RADI0 ACTIVE WASTE i LIMITING CONDITION FOR OPERATION I l j3.11.3 The solid radwaste system shall be used in accordance with a
; i PROCESS CONTROL PROGRAM to process wet radioactive waste to meet shipping
. landburialgroundrequirements.
- i APPLICABILITY: At all times.
', ACTION: f a. With the provisions of the PROCESS CONTROL PROGRAM not satisfied, suspend shipments of defectively processed or defectively packaged solidified wet radioactive wastes from the site. l l
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
t 1 ! SURVEILLANCE REQUIREMENTS l
- 4 Verification of SOLIDIFICATION of representative test specimens of
! we.11.3t waste shall be performed as required and in accordance with the PROCESS jCONTROLPROGRAM.
1 I ) i > YANKEE-ROWE 3/4 11-15 Amendment No.,pd', 104
--........-.....,+y.-y-.
g ---.--s y *m - g--- - - - g + -ye.- -
.a % e -
-.t.. . - - . -
i l 6 RADIOACTIVE EFFLUENTS
. 3/4.11.4 TOTAL DOSE Il LIMITING CONDITION FOR OPERATION 3.11.4 The dose or dose commitment to any real MEMBER OF THE PUBLIC from all station sources is limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which is limited to less than or equal to 75 mrem) over a calendar year.
l APPLICABILITY: At all times. ACTION:
- a. With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the
; limits of Specifications 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a.
i 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, calculations should be made including direct radiation contributions from the reactor and from outside storage tanks to determine whether the above limits of Specification 3.11.4 have been exceeded. If such is l the case, if not applicable to 10 CFR 50.73, prepare and submit l to the Commission within 30 days, pursuant to Specification 6.9.6, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving <onformance with the above limits. This Special Report, as required by 10 CFR Part 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from station sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report
- shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely regeest, and a variance is granted until staff action on the request is complete.
The provisions of Specification 3.0.3 and 3.0.4 are not b. applicable. SURVEILLANCE REQUIREMENTS 4.11.4 Dose Calculations: Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2 and 4.11.2.3, and in accordance with the Offsite Oose Calculation Manual (00CM). YANKEE-ROWE 3/4 11-16 Amendment No. 104
-- . . ~ _ . , ~ . .._.m.,__ . . , . . . . - . . - , , _ _ _ _ _ , . , . _ _ , _ _ _ , _ , .,_ , , _
s . e j 3.4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING f 3/4.12.1 MONITORING PROGRAM t LIMITING CONDITION FOR OPERATION
'- 3.12.1 The radiological environmental monitoring program shall be j j conducted as spectfled in Table 3.12-1.
t . ! l APPLICABILITY: At all times.
! ACTION:
l l
- a. With the radiological environmental monitoring program not being l .conducced as specified in Table 3.12-1, prepare and submit to the i i l J
; Commission, in the Annual Radiological Environmental Operating
! Report, a description of the reasons for not conducting the
' program as required and the plans for preventing a recurrence.
l Deviations are permitted from the required sampling schedule if j specimen are unobtainable due to hazardous conditions, seasonal unavailability or to malfunction of automatic sampling equipment. l If the latter, every effort shall be made to complete corrective
- action prior to the end of the next sampling period.
i
! b. With the level of radioactivity as the result of plant effluents
; ; in an environmentrl sampling media at one or more of-the
! locations specified in Table 3.12-1 exceeding the reporting 3
levels of Table 3.12-2 when averaged over any calendar quarter, r prepare and submit to the Commission within 30 days from the j ; receipt of the Laboratory Analyses, pursuant to Specification
- j 6.9.6, a Special Report which includes an evaluation of any release conditions, environmental factors or other aspects which 1 caused the limits of Table 3.12-2 to be exceeded. When more than
- i one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted'if
i i I concentration (1) + concentration (2) + .. 2 1.0 i I reporting level (1) reporting level (2) When radionuclides other than those in Table 3.12-2 are detected j and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal or greater than the calendar year limits of
- Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is 4 not required if the measured level of radleactivity was not the result of plant effluents; however, in such an event, the i condition shall be reported and described in the Annual I Radiological Environmental Operating Report.
i - 3/4 12-1 Amendment No. 99,104 YANKEE-ROWE
- i l
- l
- - - , , , - , - .-.n.-m,--m-. , , - . - . , - - -+. - ys --my.--- , .o-----+--w--- ,, my,----2-.----.--y%--r- w. . ----.,e -
.--,..m6-, ,n _ , -
I . RADIOLOGICAL ENVIRONMENTAL MONITORING l
! LIMITING CONDITICN FOR OPERATION (Continued)
- c. With milk or fresh leafy vegetation samples no longer available from one or more the sample locations required by Table 3.12-1, identify new location (s) if available, for obtaining replacement
- samples and add them to the radiological environmental monitoring program within 30 days. The specific location (s) from which samples were no longer available may then be deleted from the I monitoring program. Pursuant to Specification 6.9.5.b, identify l the cause of the samples no longer being available and identify the new location (s) for obtaining available replacement samples in the next Semiannual Radioactive Effluent Release Report and include revised 00CM figure (s) and table (s) reflecting the new location (s).
- d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
] SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be
! collected pursuant to Table 3.12-1 from the locations given in the 00CM and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1.
9 i 1 l i YANKEE-ROWE 3/4 12-2 Amendment No.[ 104 _ l
- - - -- . - - 4 .. . . . _ _ _ , _,___ ., _ , _ _ , _ _ , ,
I t l RADIOLOGICAL ENVIRONMENTAL MONITORING . i 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION i i e 3.12.2 A land use census shall be conducted to identify the location of the nearest milk animal, the nearest residence and the nearest garden" of greater than 500 square feet producing fresh leafy vegetables in each of l' the 16 meteorological sectors within a distance of five miles. l 1 APPLICABILITY: At all times. I .
- ACTION
y
- a. With a land use census identifying a location (s) which yie' ids at
] least a 20 percent greater dose or dose commitment than the j values currently being calculated in Specification 4.11.2.3, ! j identify the new location (s) in the next Semiannual Effluent ~l' 1, Release Report.
- b. With a land use census identifying a location (s) which yields' a calculated dose or dose commitment (via the same exposure pathway) at least 20 percent greater than at a location from I
which samples are currently being obtained in accordance with . Specification 3.12.1, add the new location (s) to the radiological l environmental monitoring program within 30 days if permission from the owner to collect samples can be obtained, and sufficient i sample volume is available. The sampling location (s), excluding ' l the control station location, having the lowest calculated dose ) or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Identify the new l l location (s) in the next Semiannual Effluent Release Report. l
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not
} i applicable. i SURVEILLANCE REQUIREMENTS ] 4.12.2 The land use census shall be conducted at least once per 12 months between the dates of (June 1 and October 1) by either a door-to-door - s survey, aerial survey, or by consulting-local agriculture authorities. The ' results of the land use census shall be included in the-Annual Radiological Environmental Operating Report pursuant to Specification 6.9.5.a. t "In lieu of the garden census, broad leaf vegetation sampling may be i performed at the site boundary in the direction sector with the highest i 0/Q. 1 Amendment No. 104 YANKEE-ROWE 3/4 12-9 1
I RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERCOMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on referenced radioactive materials supplied as part of an Intercomparison Program which has been approved by NRC. APPLICABILITY: At all times. ACTION:
- a. With analyses not being performed as required above report the l corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.3 A summary of the results of analyses performed as part of the above required Intercomparison Program shall be included in the Annual Radiological Environmental Operating Report. The identification of which NRC approved Intercomparison Program that is being participated in shall be stated in the ODCM. n YANKEE-ROWE 3/4 12-10 Amendment No. ,)d,104
a .A_ - ' O ( MAINcoot$NT$YSTEM EM.E Whenever the results of any steam generator tubing inservice inspec' tion fall into Category C-3, these results will be imediately reported to the Commission pursuant to 10 CFR 50.7: prior to resumption of plant operation and subsequently reported pursuant to 10 CFR 50.73. Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement
- for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.
3/4.4.11 Main Coolant systen Vents Main coolant system vents are provided to exhaust noncondensable gases and/or steam from the primary system that could inhibit natural circulation core coolin5 The OPERABILITY of at least one main coolant system vent path from the reactor vessel head or the pressuriser steen space ensures the capability exists to perform this function. The redundancy of the main coolant system vent paths, the normally closed valves and the open valve circuit breakers serve to minimize the probability (, , of inadvertent irreversible actuation while ensuring that a single failure of a vent valve, power supply, or control system does not prevent isolation of the vent path. The function, capabilities, and testing requirements of the main coolant system vent systems are consistent with the requirements of Item II.B.1 of , WUIEG-0737, " Clarification of TMI Action plan Requirements " November 1980. i l l O I YANKEE ROWE 33/4 4-13 Amendment [ , [ [ , , 104
. . _ . . - ~ **
- i
; ADMINISTRATIVE CONTROLS i' Review of all proposed tests and experiments that affect nuclear b.
safety. i l c. Review of all proposed changes to the Technical Specifications. I
! d. Review of all proposed changes or modifications to plant systems i or equipment that af?.ct nuclear safety,
- e. Investigation of all violations of the Technical Specifications including the preps stion and forwarding of reports covering evaluation and rece amendations to prevent recurrence to the Manager of Operations and to the Chairman of the Nuclear Safety Audit and Review Committee.
- f. Review of all REPORTABLE EVENTS.
- g. Review of facility operations to detect potential nuclear safety hazards,
- h. Performance of special reviews, investigations of analyses and reports thereon as requested by the Chairman of the Nuclear Safety Audit and Review Committee.
- 1. Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Security Advisor.
J. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Radiation Protection Manager,
- k. Review of every unplanned onsite release of radioactive material to the environs including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence an the forwarding of these reports to the Plant Superintendent and to the Nuclear Safety Audit and i Review Committee.
l
- 1. Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE l DOSE CALCULATION MANUAL.
AUTHORITY _ 6.5.1.7 The Plant Operation Review Committee snall:
- a. Recommend to the Plant Superintendent, written approval or disapproval of items considered under 6.5.1.6(a) through (d) above.
YANKEE-ROWE 6-8 AmendmentNo.[,AOrlf
ADMINISTRATIVE CONTROLS I b. Proposed changes to equipment or systems which involve an
*i unreviewed safety question as defined in Section 50.59, 10 CFR.
t
, c. Proposed test or experiments which involve an unreviewed safety question as defined !n Section 50.59, 10 CFR.
l
*I Proposed changes to Technical Specifications or this Operating-i d.
License,
!l
- e. Violations of codes, regulations, orders, Technical
.i Specifications, license requirements, or of internal procedures
;I or instructions having nuclear safety significance.
I i f. Significant operating abnormalities or deviations from normal and
! expected performance of plant equipment that affect nuclear safety, defined as Plant Information Reports.
.i I
- g. All REPORTABLE EVENTS.
, : h. Reports and meeting minutes of the Plant Operation Review Committee.
- i. Perform special reviews and investigations and render reports thereon as requested by the Vice President of Operations.
I 1 ljAUDITS Ii 6.5.2.9 Audits of facility activities shall be performed under the cognizance of the NSAR Committee. These audits shall encompass: i
- a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per-12 months, 25%.
- b. The performance, training and qualification of those members of
! the facility staff who have a direct relationship to operation, maintenance or technical aspects of the plant, at least once per i
12 months, 25%. .
- c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months, 25%.
- d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months, 225%.
- e. The Facility Emergency Plan and implementing procedures at least once per 12 months, 25%.
YANKEE-ROWE 6-11 Amendment No. % HT, J ( 104
s .
; ADMINISTRATIVE CCNTROLS
' l j 6.5.3.2 An inspection and audit of the fire protection and loss prevention
- 4 ,
program shall be performed by a qualified outside fire consultant at least once per 36 months. 6.6 REPORTABLE EVENT ACTION 4 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
- a. The Commission shall be notified and a report submitted pursuxnt to the requirements of Section 50.73 to 10 CFR Part 50, and
- b. Each REPORTABLE EVE T shall be reviewed by the PORC and the
' I results of this review shall be submitted to the NSAR Committee 1 and the Manager of Operations. i i 6.7 SAFETY LIMIT VIOLATION J l 6.7.1 The following actions shall be taken in the event a Safety Limit is i violated: 1
- a. The facility shall be placed in at least HOT STAND 8Y within one hour.
- b. The Safety Limit violation shall be reported to the Commission, the Manager of Operations and to the NSAR Committee within 24 ,
i hours.
. c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the Plant Operation Review Committee. This..
report shall describe (1) applicable circumstances preceding the
- violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
~
- d. The Safety Limit Violation Report shall be submitted to the Commission, the NSAR Committee and the Manager of Operations within 14 days of the violation.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained - that meet or exceed the requirements and recommendations of Sections , 5.2-5.2.9 and 5.3 of ANSI N18.7-1972 and Appendix "A" of Regulatory Guide l 1.33, Revision 2, except as provided in 6.8.2 and 6.8.3 below. The written - procedures shall also cover the activities relating to:
- a. FIRE PROTECTION PROGRAM implementation.
- b. PROCESS CONTROL PROGRAM implementation.
- c. OFFSITE DOSE CALCULATION MANUAL implementation.
- d. Quality Assurance Program for effluent'and environmental monitoring, using the guidance in Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1, April 1975.
6-13 Amendment No.[, , pf 104 YANKEE-ROWE 1
. _ _ . . _ . _ . . . . ,_._._....__.._._.._.._...-..._..__._.._._._.,_.a
l l ADMINISTRATIVE Cormt01.5 l l 6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the Plant Operations Review Committee and approved by the Plant Superintendent prior to implementation and reviewed periodically as set forth in administrative procedures. 6.5.3 Procedures that have been developed as a result of changes lefined in 10 CTR 50.59(a)(2) shall be independently reviewed to verify that the , implementing actions do not constitute an unreviewed safety question. Those reviews shall be performed by Nuclear Service Division personnel having qualifications at least equivalent to those specified for NSAR Committee membership in 6.5.2.3. The procedures ~shall be approved by the Manager of Operations, NSD. , 6.8.4 Temporary char.ges to procedures of 6.8.1 above may be made provided:
- a. The intent of the original procedure is not altered.
- b. The change is approved by two members of the plant management staff, -
at least one of whom. holds a Senior Reactor Operator's License.
- c. The change is documented, reviewed by PORC and approved by the Plant Superintendent within 14 days ci implementation.
6.9 REP 3RTINC EQUIEM"j"g The following identified reports shall be submitted pursuant to 10 CFR 50.4
~
The reporting requirements of Specifications 6.9.1, 6.9.2, and 6.9.3 are in accordance with Revision 4 of Regulatory Guide 1.16, " Reporting of Operating i Information - Appendix A Technica1 Specifications". I ROUTINE REPORTS
~., . ~
6.9.1 Startun Report. 'A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) j amendment to the license involving and planned increase in power level, (3) i installation of fuel that has a different fuel ' supplier, and (4) modifications that may have significantly altered the nuclear, ther=al, or hydraulic performance of the plant. The report shall address each of the tests identified in the THSR and shall in general include a description of measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall miso b9 described. Any additional specific details required .in license conditipns based on other commitmaps shall be included in this report.
- YANKEE-ROVE -
6-14 Amendment No. 104 { , i 6*
~ ADMINISTRATIVE CONTROLS Startup reports shall be submitted within (1) 90 days following completion of the startup test program (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, c9mpletion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed. 6.9.2 Annual Report. Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. Reports required on an annual basis shall include:
- a. A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions, (a) e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and. refueling.
The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the whole body dose received f rom external sources shall be assigned to specific major work functions.
- b. Any other unit-unique reports required on an annual basis.
- c. Documentation of all challenges to the pressurizer Power-Operated Relief Valves (PORVs) or safety valves.
- d. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.7. The following information shall be included: (1) Reactor power history starting 48 hours prior to the first sample in which the limit was exceeded; (2) Results of the last iso topic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis af ter the radioiodine activity was reduced to less than limit. Each result should include date and time of sampling and the radiciodine concen-trations; (3) Clean-up system flow history starting 48 hours prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The i time duration when the specific activity of the primary coolant excpe,dedtheradiciodinelimit.
(a) This tabulation supplements the requirements of Section 20.407 of 10 CFR Part 20 YANKEE-ROWE 6-15 Amendment No. fE, $@, 83 104
4 lADMINISTRATIVECONTROLS 6.9.3 Monthly Operating Report. Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis pursuant to _.10 CFR 50.4, to arrive no later than the 15th of each month following the calendar month covered by the report. YANKEE-ROWE 6.15a Amendment No. 104 l
4 4 6 .2g u u -.._m.>- ,t . a_ 9 4 l ADMINISTRATIVE CONTROLS i ! . 6.9.4 . DELETE
-9
( f s 0 4 i t i i YANKEE-ROWE 6-16 AmendmentNo.%,[, 104
j ADMINISTRATIVE CONTROLS l I l t O i
., i .
THIS PAGE INTENTIONALLY LEFT BLANK l. I e I O s Amendment No. 104 YANKEE-ROWE 6-17 , , 9
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y -7 / O r S L O e 4 O ADMINISTRATIVE CONTROLS i
. I i
i . I i ! i , l 1 l THIS PAGE INTENTIONALLY LEFT BLANK . l*! l t i! * , iI ! l i t a ' 1 1 l i l l I ! l 1 i i, I t
- i.
b i l l 4 l YANKEE-ROWE 6-18 AmendmentNo.J4./,A104
F. ACMINISTRATIVE CONTROLS i
-l l 6.9.5 Unique Reporting Requirements
- a. Environmental Radiological Monitoring
- 1) Routine radiological environmental operating reports i covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.
- 2) The annual radiological environmental operating reports shall include summaries, interpretations and an analysis of
- trends of the results of the radiological environmental j surveillance activities for the report period, including a
. comparison with operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results
- of the land use censuses required by Specification 3.12.2.
i l The annual radiological environmental operating reports l shall include summarized and tabulated results of all radiological environmental samples taken during the report period pursuant to the Table and Figures in the 00CM. In l the event that some results are not available for inc10sion with the report, the report shall be submitted noting and
- explaining the reasons for the missing results. The missing i data shall be submitted as soon as possible in a j supplementary report.
i i 1 i I YANKEE-ROWE 6-19 Amendment No. g, Jef 104
O
~
4 1 i I 1 i j ADMINISTRATIVE CONTROLS I i
- location) sh'all be included in these reports. Foi batch or discrete i gas volume releases, the seteorological conditions concurrent with j the time of release of radioactive sacerials in gaseoua effluents ,
i (as determined by sampling frequency and seasurement) shall be used f or determining the gaseous pathway doses. For radioact'ive ! asterials released in continuous effluent streams, quarterly average j meteorological conditions concurrent with the quarterly release ' t period shall be used for determining the gaseous pathway doses. The ; j assessment of radiation doses shall be performed in accordance with 1 the Off site Do'se Calculation Manual (ODCH). ' i The radioactive effluent release report to be submitted 60 days af ter January 1 of each year shall also include an assessment of i { j radiation doses to the .likely most exposed real MEMBER (S) 0F TMZ
. PUBLIC from reactor releases (including doses from primary effluent '
i pathways and direct radiation) for the previous calendar year to j show conformance with 40 CFR 190, Environmental Radiation Protection j Standards for Nuclear Power operation, if Specification 3.11.4 has ! f been exceeded during the calendar year. . , { 1 The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) ! ] shipped offsite during the report periods. 1, t
- s. Container volume.
i b. Total curie quantity (specify whether determined by sensurement or j estimate). } 2 c. Principal radionuclides (specify whether determined by sessurement or estimate). j d. '
- Source weste and processing employed (e.g., devatored spent resin, compacted dry waste, evaporator bottons).
e. Type of container (e.g., LSA Type A Type 3, Large Quantity), and f. Solidification agent or absorbent (e.g., cement, asphalt, "Dow"). The Radioactive Iffluent Release Reports shall include a list and description of unplanned releases form the site to site boundary of radioactive asterials in gaseous and liquid affluents made during the reporting period. i } ' The Radioactive affluent Release Reports shall include any abanges made
- during the reporting period to the PROCESS CONTROL PROGRAM (PCF) and to the OFF-SITE DOSE CALCULATION MANUAL (00CM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to specification 3.12.2.
YANKEE-ROWE 6-11 Amendaent No. p ,104 i . 1 ) i , L=- == = = = = " - =- = " = " - - - ~ ~ ~~~
r E ADMINISTRATIVE CONTROLS 6.9.6 Special Reports. Specialreportsshallbesubmittedpursuantto10CFRl 50.4 wit 11n the time period specified for each report. These reports shall
.be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:
- a. (Deleted)
- b. (Deleted) l
- c. Inoperable Meteorological Monitoring Instrumentation.
Specification 3.3.3.3.
- d. Sealed Source leakage in excess of limits, Specification 3.7.6.
- e. Fire Detection Instrumentation, Specification 3.3.3.4.
- f. Fire Suppression Systems, Specifications 3.7.10.1, 3.7.10.2, 3.7.10.3, 3.7.10.5, and 3.7.10.6.
l
- g. Liquid Effluents, Specifications 3.11.1.2, and 3.11.1.3.
e l h. Gaseous Effluents Specifications 3.11.2.2, 3.11.2.3 and 3.11.2.4 t ( , 1. Total Dose, Specification 3.11.4.
- j. Radiological Environmental Monitoring, Specification 3.12.1.
l I
- k. Radiation Monitoring, Specification 3.3.3.1.
4 .
!! 1. Structural integrity, ASME Code Class 1, 2 and 3 Components.
Specification 4.4.9.1.
, m. Steam Generator, Specification 4.4.10.5.b.
I e n. Containment Vessel Structural Integrity, Specification 4.6.1.6. 6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:
- a. Records and logs of facility operation covering time interval at each power level,
- b. Records and logs of principal maintenance activities, inspection repair and replacement of principal items of equipment related to nuclear safety.
- c. ALL REPORTABLE EVENT reports submitted to the COMNISSION.
{
\ d. Records of surveillance activities, inspections and calibrations l required by these Technical Specifications.
Yankee-Rowe 6-22 Amendment No. f4', JMI, pf, % 194 i _ . . . - e. .
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