ML20062D166

Requests Amend to Oper Lic Tech Specs Limiting Maximum Boron Concentration in Sit'S & Rwt'S to 2200ppm,allow Lesser Shutdown Cooling Flow When Reactor Coolant Loop Partially Drained,& Add Loss of Field Trip to DG Surveillance

ML20062D166
Person / Time
Site:	Calvert Cliffs
Issue date:	11/13/1978
From:	Lundvall A BALTIMORE GAS & ELECTRIC CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 7811200206
Download: ML20062D166 (30)

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BALTI M O RE GAS AN D ELECTRIC CO M PANY GAS AN D ELECTRIC BUILDING

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D A LTI M O R E. M A RY LA N D 212 03

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November 13, 1978 se.

Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Subject:

Calvert Cliffs Nuclear Power Plant Units Nos. 1 & 2, Dockets Nos. 50-317 & 50-318 Request for Amendment to OneratinT Licenses Baltimore Gas and Electric Company hereby requests an amendment to its operating licenses DPR-53 for Unit No.1 and DPR-69 for Unit No. 2 vith the following proposed changes to the licenses and technical specif-ications. The parenthetical reference codes are for BG&E use.

PROPOSED CHANGES

1. (BG&E Ref. No. 77-lh9) DPR-53 and DPR-69: Change paragraphs 3.1.2.8.b.2, 3 51.c, and 3.5.h.b as shown on attached pages to limit the maximum boron concentration in the SITS and RWTs to 2200 ppm.

2. (78-13) DPR-53 and DPR-69: Add exception to paragraph h.9.8 as shown .,

on attached page to allov lesser shutdown cooling flow when reactor

• coolant loop is partially drained.

3 f78-3h) DPR-53 and DPR-69: Add loss of field trip to DG surveillance i t. paragraph k.8.1.1.2.c.3 (c) as shown on attached sheet.

h. (78 h3) DPR-53 and DPR-69: Change paragraph 5.6.2.c(1) as shown on attached sheet to make radioactive liquid effluent reporting level conform to specification paragraph 2.3. A.T.

5 (78-9h) DPR-53 and DPR-69: Change paragraphs h.6.3.1, b.6.6.1, b.7.7 1, and h.912 as shown on attached pages to delete requirement for 18-month air flow distribution check across HEPA and charcoal filters and add requirement to perform the check after applicable maintenance in accordance with the In-Place Testing Criteria, paragraph C.5.b. of Regulatory Guide 1.lh0, March 1978.

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6. (78-112) DPR-53: Change Table 3.7 h as chovn on attached pages to make administrative corrections to hydraulic snubber locations and accessibility and to add one snubber.

7 (78-120) DPR-53 and DPR-69: Change Table 3.6-1 as shown on attached pages to allow valves 130M3-1 and -2 to be opened under administrative control.

8. (78-131) DPR-53 and DPR-69: Change the reporting requirements in paragraph 2.2.2 for treatment chemicals from semi-annual to the j Annual Environmental Operating Report as shown on the attached page.

9 (78-132) DPR-53 and DPR-69: Change paragraph b.9.6 as shown on the attached page to specify the dry versus wet capacity of the refueling machine and to clarify the applicability of the capacity checks of the cmchine.

10. (78-133) DPR-53 and DPR-69: Change Figures 6.2-1 and 6.2-2 as shown

( on the attached pages to update the organizational control of the Calvert Cliffs Security Force.

11. (78-150) DPR-69: Delete condition 2.C.3 of the Unit No. 2 Operating License as shown on the attached page to account for the recent modif-  ;

ication made to the steam generator feed ring. '

4 1

DISCUSSI0lt OF PROPOSED CHANGES  !

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1. A total of 75 cubic feet of trisodium phosphate (TSP) is stored in j each contaimment sump in dissolving baskets to mix vith the water which i has collected in the sump due to safety injection and containment spray {

operation following a LOCA. It has been determined that the maximum allowable concentration of boron contained in the Refueling Water Tanks and Safety Injection Tanks must be limited to 2200 ppm in order to

( ensure that the resultant pH of the sump water 'does not fall belov 7.0 after the TSP has been fully dissolved.

2. When a Lov Pressure Safety Injection pump is operating in the shutdown cooling mode with the reactor coolant hot leg drained to a level below the midpoint of the pipe, it has been observed that there is insufficient water in the hot leg to allow proper LPSI sump operation without result-ing in a drastic pump flow reduction probably due to air being sucked l into the pump inlet along with the water in the tot leg. If the LPSI pump speed was reduced such that the maximum flow rate was 1500 gpm, the water level in the partially-drained hot leg would be sufficient to ensure a uniform supply to the pump suction. The reduced flow of

1500 gpm vill not compromise the intention of the,present technical specification, i.e. to provide core cooling and to prevent boron stratifi-cation, since Technical Specification paragraph 3/h.l.l.3 requires that a flow of at least 3000 gpm be maintained while making boron concen-tration reductions, thus precluding boron stratification, and since operational experience while in Mode 5 has shown that more than sufficient i core cooling is provided by a pu=p flow rate of 1500 gpm.

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3 The %ss of Field" function trips the diesel generator output breacker l and is retained during au SIAS. It is correctly itemized on page 8-20 l of the FSAR but was inadvertently omitted from the Technical Specifications. ,,

18 The reporting level for the release rate of radioactive liquid I effluents is correctly specified in Appendix B Technical Specif: cation paragraph 2 3.A.7 as 2.5 curies per unit per quarter. The prop ,ed change to paragraph 5.6.2.c of those specificatione vill put it in  ;

agreement with the former paragraph. This change has been discussed i with the Office of Inspection and Enforcement Inspector (Region I), '

and he has concurred with this proposed action.

5 This change deletes the requirement to check air flow distribution l every 18 months and adds a requirement to check the distribution' after maintenance which may have an effect on the distribution. This request is consistent with the March 1978 (comment copy) version of Regulatory .'

Guide 1.1h0. r

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6. The indicated chanEes to the Safety blated Hydraulic Snubbers table I are being proposed:

a. To administrative 1y correct the elevations shown for certain snubbers; ,

b. to correctly indicate the radiation zone and accessibility of i certain snubbers based on operating experience; f I

c. to add a heretofore unlisted snubber. The snubber in question has i been listed in surveillance test procedures and has been subject to r surveillance at the periodicity specified in the Technical Spec-ifications.

'7 . The proposed change vill allov valves 130M3-1 and 130M3-2 (Penetration

( No. 39) to be open on an intermittent basis under ad inistrative control. i The low pressure safety injection headers must be recirculated and saepled to determine boron concentration prior to entering the shutdown cooling lineup. These valves must be open to allow recirculation and to enabic sampling outside of containment. Otherwise, the plant must l-be in node 5 prior to opening the valves.  ;

l

8. This change makes the requirement for reporting the use of treatment I chemicals consistent with section 5.6.1.a of the Appendix B Technical l Specifications, where it specifies nonradiological reports as being made in the Annual Environmental Monitoring Report.

9 The specified lifting capacity of the refueling machine is 110 percent ,

of the dry weight of a fuel assembly containing a CEA. The dummy fuel assembly was designed to provide a veight of 1550 pounds dry but only weighs lh20 pounds in vater (due to buoyant effects). The indicated clarification allows the capacity test to be conducted with the refueling .

Page k pool either dry or flooded to account for this condition,and defines the capacity test as being required prior to the use of the hoisting mechanism for moving fuel or fuel containing a CEA within the reactor vessel.

10. The Calvert Cliffs Security Force has recently been placed under the cognizance of the Real Estate and Office Services Department consis-tent with other Company security functions. The proposed change reflects this organizational modification.

11. During the past refueling outage for Unit No. 2, a modification was made to the main feed ring which placed the discharge ports on the ring at the top rather than the bottom. This modification now allows the ring to become filled with feedvater prior to that water exiting the ports into the steam generator. The purpose of the license condition was to prevent feeding the steam generator too rapidly through the main feed ring and thus possibly causing a flow instability. The recent

( modification now allows the steam generator to be fed from a level below the feed ring at an unrestricted rate.

DATES CHANGES REQUIRED (1) Not specified (7) January 1979 (2) January 1979 (8) June 1979 (3) Not specified (9) April 1979 (b) December 31, 1978 (10) Not specified (5) April 1979 (11) As soon as possible (6) Not specified REVIEW The proposed changes have been reviewed by the Plant Operations

'and Safety Review Cb=mittee and the Off-Site Safety and Review Committee, I and they have concluded that the changes vill not result in an undue risk to the health and safety of the public.

BALTIMORE GAS AND ELE COMPANY

, By: /, -

AJ M. E. Luhdgall, Ji . f Vice Preside 6t - Supply STATE OF MARYLAND '

TO WIT CITY OF BALTIMORE i

Mr. A. E. Lundvall, Jr. being duly sworn states that he is Vice President of the Baltimore Gas and Electric Company, a corporation of the State of

,* thryland: that he executed the foregoing Amendment for the purposes therein set forth: that the statements made in said Amendment are true and correct to the best of his knowledge, information and belief: and that he was L

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authorized to execute the Amendment on behalf of said corporation.

WITNESS My Hand and Notarial Seal.

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L/A A Notary Public My Commission expires: -

L(4/ //! b cc: J. A. Biddison, Esquire 9

, G. F. Trowbridge, Esquire

Mr. E. L. Conner, Jr. - NRC

] Mr. P. W. Kruse - CE j Mr. J. W. Brothers - Bechtel ,

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tto FeL %t49 REACTIVIT7 CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.8 At least two of the following three borated water sources shall be OPERABLE:

a. Two boric acid storage tank (s) and one associated heat tracing circuit per tank with the contents of the tanks in accordance with Figure 3.1-1 and the boron concentration limited to < 8%,

and

b. The refueling water tank with:

1. A minimum contained borated water volume of 400,000 gallons, 2200

2. A boron concentration of between 1720 and-2MG-ppm,

3. A minimum solution temperature of 40*F, and

4. A maximum solution temperature of 100*F in MODE 1.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With only one borated water source OPERABLE, restore at least two borated water sources to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within tne next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a SHUTDOWN MARGIN equivalent to at least 1% ak/k at 200*F; restore at least two borated water sources to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.1.2.8 At least two borated water sources shall be demonstrated OPERABLE:

a. At least one per 7 days by: .

1. Verifying the boron concentration in each water source,

2. Verifying the contained borated water volume in each water source, and

3. verifying the boric acid storage tank solution temperature.

b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWT temperature when the outside air temperature is < 40*F. I CALVERT CLIFFS - UNIT 1 3/4 1 16 Amendment No. 21

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AC0 h 7-149 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

SAFETY INJECTION TANKS LIMITING CONDITION FOR OPERATION 3.5.1 Each reactor coolant system safety injection tank shall be OPERABLE with:

a. The isolation valve open,

b. A contained borated water volume of between 1113 and 1179 cubic feet of borated water (equivalent to tank levels of between187and199 inches,respectively), 3 he"WC M

c. A ~* 4 - boren concentration o 1720 l$C and TZOO PPM, Ad.

d. A nitrogen cover-pressure of between 200 and 250 psig.

APPLICABILITY: MODES 1, 2 and 3.*

ACTION:

a. With one safety injection tank inoperable, except as a result of a closed isolation valve, restore the inoperable tank to OPERABLE status within one hour or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

b. With one safety injection tank inoperable due to the isolation valve being closed, either imediately open the isolation valve or be in HOT STANDBY within one hour and be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REOUIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:

1. Verifying the contained borated water volume and nit ogen cover-pressure in the tanks, and

2. Verifying that each safety injection tank isolation valve 2 is open.

• With pressurizer pressure > 1750 psia. l l

CALVERT CLIFFS - UNIT I 3/4 5-1 48 12 gy II H -4 7 " 4 Aud g g4 g i

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FcA H49 EMERGEf.CY CORE COOLING SYSTEMS I

REFUELING WATER TANK LIMITING CONDITION FOR OPERATION 3.5.4 The refueling water tank shall be OPERABLE with:

a. A minimum contained borated water volume of 400,000 gallons, ,

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b. A boron concentration of between 1720 and +Me ppm,

c. A minimum water temperature of 40*F, and l d. A maximum solution temperature of 100*F in MODE 1.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the refueling water tank inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS

( 4.5.4 The RWT shall be demonstrated OPERABLE:

a. At least once per 7 days by:

1. Verifying the contained borated water volume in the tank, and

2. Verifying the boron concentration of the water.

b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWT temperature when the outside air temperature is < 40*F. l CALyERTCLIFFS-UNIT 1 3/4 5-7 Amendment No. 21 g, n ..

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Fc/L ~7&-l 3 REFUELING OPERATIONS COOLANT CIRCULATION LIMITING CONDITION FOR OPERATION 3.9.8 At least one shutdown cooling loop shall be in operation.

APPLICABILITY: MODE 6.

3 ACTION:

a. With less than one shutdown cooling loop in operation, except as provided in b. below, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System. Close all containment penetrations providing direct access from the containment atmosphere to.the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The shutdown cooling pumps may be de-energized during the time intervals required for local leak rate testing of containment penetration number 41 pursuant to the requirements of Specification 4.6.1.2.d, provided 1) no operations are permitted which could cause dilution of the reactor coolant system boron concentration, 2) all CORE ALTERATIONS are suspended, and 3) all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere are maintained closed,

b. The shutdown cooling loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs,

c. The provisions of Specification 3.0.3 are not applicable. i i

SURVEILLANCE REQUIREMENTS 4.9.8 A shutdown cooling loop shall be determined to be in operation and circulating reactor coolant at a flow rate of > 3000 gpm at least I once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.Howcwg A tl<. Mi i dAnswd +c c. fud be2N St Ndh cf fL . kft hh repie'vd dn.>rz%,u 3 lStop, IE81 CALVERT CLIFFS - UNIT 1 g7 '

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M 7 E ELECTRICAL POWER SYSTEMS SURVEILLAf1CE REQUIREMENTS (Continued) e 4.t.i.t.l.c.b) 3.Verifying E*hthe36 dieselsW startsk AM from WS"MN ambient condition "'"Fi(

on the auto-start signal, energizes the emergency busses with permanently connected loads, energizes the auto-connected emergency loads through the load sequencer and operates for > 5 minutes while its generator is loaded with the emergency loads, c Verifying that all diesel generator trips, except engine overspeed, crankcase pressure high, lube oil

(

y pressure low, generator ground overcurrent, and l 4 generator differential, are automatically bypassed on a Safety injection Actuation Signal.

4 Verifying the diesel generator operates for > 60 minutes while loaded to > 2500 kw.

5. Verifying that the auto-connected loads to each diesel generator do not exceed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating of 2700 kw.

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Shanp(D FcE 7f-43 (with a copy to the Director, Office of Nuclear Reae.or Regulation). The written report shall (a) describe, analyze and evaluate the occurence, (b) describe the cause of the occurrence, and (c) indicate the corrective action (including any l

significant change in procedures) taken to preclude repetitien of the occurrence and to prevent similar occurrences involving similar compenents or systems.

The significance of an unusual or apparently important event with regard to environ-mental impact may not be obvious or fully appreciated at the time of occurrence.

In st.ch cases the NRC shall be informed of changes in the licensee's assessment of the significance of the event and a corrected report shall be submitted as expeditiously as possible.

5.6.2.b Ncnroutine Radiological Environmental Operating Reports

(

t If a confirmed measured level of radioactivity at any offsite location in any '

environmental medium exceeds ten times the " background" value, a written report shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) within ik days after confir=atien.

The report shall include an evaluation of any releese conditions, environmental factors, or other aspects necessary to explain the results.

5.6.2.c Nonroutine Radicactive Effluent Reports (1) When the release rate of radioacuive liquid effluents, excluding tritium and

( 2.50 wunir per pam cph 23. A 7 noble gases, exceeds -1rOS-cur:,esgduring any calendar quarter e licensee shall i l

notify the Director of the NRC Regional Office (with a ecpy to the Director, Office of Nuclear Reactor Regulation), within 30 days, identifying the causes and describing the proposed program of action to reduce such release rates.

(2) When the annual projected release rate of radieretive caterials in gasecus, vastes, averaged over a calendar quarter, exceeds twice the annus1 objectives, the licensee shall notify the Director of the NRC Regional Office (with a ecpy to the Diructor, Office of Nuclear Reactor Regulation) within 30 days, identifying the causes and describing the proposed program of action to reduce such release rates.

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SURVEILLANCE REOUIREMENTS (Continued) - *- ,'

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a. Emptying one entire bed from a removed adsorber s . . ).s tray.. mixing the adsorbent thoroughly, and obtaining Ni

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a demonstrated OPERABLE by also: '

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U' Verifying' that the'charcoa1 adsorbers re::nve > 99% of

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with ANSI N510-1975 while operating the filter train s-

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.#.e. ~... -filters and charcoal adsorber banks is < 6 inches Water

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CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)

e. After each complete or par tial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove > 99% of the DOP when they are tested in place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 20,000 cfm i 10%.

f. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove

> 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 20,000 cfm 110%.

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L Glr-  %) hbe m within : 20% of the average flow per unit when tested in sesordance with the provisions of Section 9 of " Industrial Ventilation" and Section 8 of ANSI N510-1975.

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a) Emptying one entire bed from a removed adsorber tray, mixing the adsorbent thoroughly, and obtaininN,.. '

samples at least two inches in diameter and with r F  ;

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• - tray, mixing the adsorbent thoroughly, and obtaining' - 1 9 .~ - samples at least two inches in diameter and with a E ~ -

. 1ength equal to the thickness of the bed. '

- . . < I.. . .

,d " w,.

Subsequent to reinstalling the adsorber tray us'ed'for :

P .- gbtaining the carbon sample, the system shall be demon . io

, . ,; 3 .sttated.0PERABLE by also: '

a) ' Verifying that the charcoal adsorbers remove > 99%,.4.f...~

2 of a halogenated hydrocarbon refrigerant test gas X 6

• when they are tested in-place in accordance with N-ANSI N510-1975 while operating the ventilation system

, at a flow rate of 2000 cfm + 10%, and , .,'; c

~

b) Verifying that the HEPA filter banks remove > ', '

. of the DOP when they are tested in-place in accordance 99%

with ANSI N510-1975 while operating the ventilation . .. .

3 sy  :

q.l.(..I M &M pedst " atrm. a floweAm{ ate of 2000 cfm + 10%.airftwtva.,%yLe& 4(;;

d. At least once per 18 months by:

. M. .

1. Verifying that the pressure drop across the combined HEPA

( ,

.' filters and charcoal adsorber banks is < 6 inches Water t

• Gauge while operating the filtar train at a flow- '

...y rate of 2000 cfm +- 10%.  ?-

)j

~,

'r^ -

7.

6. Uj' ; tMt M =b flevr*6tMtttn .. uni .w m wundi

• 20% acrn" TA n iters and charcoa s in w. L .- '4=n tested a .; . ,

-nrTi~cordance with ANSI N510-1975. . , .

I Verifying that the filter train star'ts on a Containment3 3.

Isolation Test Signal. .,

s

. . - .  :. s.

w

-.2 t . ~

,+ be-. .

.- 5 . j . . r.i-: .' .. z. $A.h- f .. ' :.. i. '

+:U

- : ;.R*-f.f &N;V'-N ;? .-

N

(~f,. !. .- CALVERT CLIFFS - UNIT 1 . ' w.;-3/4. 6-30

"'I

-.: a. .

...= - .

. v.

.s.. > ;

-4 m .. .. * .

FEB i 1 , y. .

v; .

W ' ...; .,9 . ... a.~ . . n .. ~ % . UU.tT.1? ul.' && ,h I: ?s 5.. e. . -a*Sf d 3-hr;WJ: h. ?

?.

..:. .-: m. i.e.n...w.g Q.- -:;.-;y

n. .L.g.

. . g. :.p:.y;;;,. a.

. : QL

. i .;. -,. .nav ,

 :. . . w.&,.

.ea;.v. c n.e .M,..a- v. :.. :.,. v-n.

a .- 1w:.;:  ;*:..n:w + . o,c: gA g.. u.. m...w u.aa:.A  :' p a:.y.-~.2.&m..='~;

,.; L.';. ] s+f;%.~s.? A.a.- s = .

ra ' e-s CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

e. After each complete or partial replacement of a HEFA filter bank by verifying that the HEPA filter banks remove > 99" of the 00P when they are tested in-place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 2000 cfm + 10%. ,

f. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove

> 99% of a halogenated hydrocarbon refrigerant test gas when p

i they are tested in-place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 2000 cfm

-+ 10%.

l!

. k Att d*1 U b h ett Y hff$hubh b / 0" "#'

d!!* h hobub S within : 20% of the average flow per unit when te>ted in accordance with the provisions of Section 9 9f " Industrial Ventilation" and Section 8 of ANSI N510-1975.

(

igg , I CALVERT CLIFFS - UNIT 1 3/4 6-31 N/

J

,- m. y a :- -

g&. >1

.e yr r w r ;r.

n.

- ~-

. q . .w:.;..

4 ,,j . ..., g , 4 ;..

<ac;ygzf

. . , *. . -C -: <  :.

J

- ~. ..

• "'_' - kg fy r *:' ,.

( .

• . c.

, PLANT SYSTEM i .*

- Q .e .. ,.. -.

SURVEILLANCE REOUIREMENTS (Continued) -

l l

2 Verifying within 31 days after removal that a lebratory, analysis of at least two carbon samples demonstrate a .. , .'

removal efficiency of > 90% for radioactive methyl iodide r" ti'

!' '. when the samples are tested in accordance with ANSI N510 ; i .*c.;.,-

1975 (130*C, 95% R.H.) and the samples are prepared by . .,. Y ' 17,.2 .

]

.]7 k., . ..

either: ,

',. ' . , " :cV@. .

a . .. - 1, .

i

' .c'. 7~ .. . $ . a)' Emptying one entire bed from a removed adsorber' * '<c

' , '7 .#j :".' -.. tray, mixing the adsorbent thoroughly -and obtaining '.; M f.w l e 1

.z ' t t samples at least two inches in diameter and with a;.. . y 4,

1ength. equal to the. thickness of the bed, or , s. - . c. . *  !

s .

j 1 -

. . . . . .- c . i

~ *b)' Emptying a longitudinal sample from an adso'rber j]~ .. e j

c,. tray, mixing the adsorbent thoroughly, and obtaining ,1 1

.j '

samples at least two inches in diameter and with sa .,.i,,,,,

j '

' length equal to the thickness of the bed. r..

s ..

.', p . ' . 3- -

2 T ,

~ '

Susequent to reinstalling the adsorber tray used'for E.,

j

• ~

4 ,

obtaining the carbon sample, the system shall demonstrated, .

_. , OPERABLE by also

,

3

, s,.. . . -

! . - . ..; a) Verifying that the charcoal adsorbers~ remove > 99%' % ),:. -

.'.. ' , , ,. e Tof a halogenated hydrocarbon refrigerant test gas -

j P ., '

when they are testedMn-place in accordance with 1

. 7 . ..-..!.

t-

..+ v

.s ANSI.' N510-1975 while operating the ventilation

-.7.Y.

, ' . .' .i ~ '

, p;m -

., , ,, v. p * ,y,c ' .:l-dystem at a flow rate of 3000 cfm + 10%, and "' --

. g '

"'.s.

i 4

, Verifying that the HEPA filter banks remove 199% ofi,-

j

.'[ ,

-- 5 .

' [.*

' b) . ;-

( . ...

--  : j . . -

3. , '. the 00P when they are tested in-place in accordance ,'

' '- ~

. . . . with ANSI N510-1975 while operating the ventilation 1 -

, system at a flow r te of 3000 cfm + 10%. -

j . , :, ,, 1 . &.'}.~).\ ~YSCCS Puy rw.' tx*v. apt 4 -

d. At lea.st.once per 18 months by:y*. .t ..,,,,.7 .td shHh MiQ vgd$s M

-.C Nr ..:,

t d . 4. , .

. c{. ..

4 .1  : z.f .% 1,."

~

Verifying that t'he ' pressure drop across the combined HEPAY. )~ l ~f

! ,;f

... f.' . -% .: ..?' '-

ffilters and charcoal.adsorber banks is <.4 inches Water .

7..' . m

_. Gauge while. operating the filter train:at a . flow' rate-of 4

t 4 - -

3., -

3000 cfm + 10%.  ;: - !. < .

2 .i -

'$' 2. v e c i .~, 'r.;; M we flow' diet.=4tnrtTon is uniform . :,

.i' within 20% a - ;Gn ni .r: "d charcoal adsorbers

c. "-

w in accordance with ANSI N51u-avi . *~

. .,7 -

u... . , . . _ + m t . . b..,m. h..- -

~

5

• s; ~~; .. . . . _ -

. . --  : L

. . j% . h. . '. . j' - ... . if. . .

K ' :- a.y ;;% ,( ~n :p:%.L<,~,y, , &.v. ,.Q

.m -

y .y , .. . e .;. .-.. ,;-. : , . .<

, . :.,e. . . .. . .

.t.g.e.. .v .. - -

- .. . , 1,.

. w. . , p- ,.

..m .. .

.r.,..,.. .

.... - 1...s

n. .n.s .v: .

A f.. ~f '.

!  ; d LVERT.,Cl.IFFS-UNIT.1 7,23 T

.e

.J. .. ,g.: 3/4 ' s M. ,

Fp+ jy c.w. u%,g.3;eb.h.g8d Q;

. i*. ,* ,. l . j .' a .lm

. ,i.. . .D'~ fh.-

. .. n 2..+.

t ,. . l , b=r ,. .} ) ,_.

. - O * ^ 'c', . J.f

• 2%".E.;~~llf, _. .h: .It f*f ~l,*

lh D

• wW a.l. K m ;Y'..  : w.+..m  ? .: f .9.h'? m..*$u.?w.W:hi.$kf$.N."$kYf.YQY$.

.wux&ummmw.

4

• 2-h  :

PLANT SYSTEMS

. s' SURVEILLANCE REQUIREMENTS (Cnntinued)

e. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove > 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the filter tratr, at a flow rate of 3000 cfm i 10%.

f. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove

> 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 i while operating the filter train at a flow rate of 3000 cfm i 10%.

. r indt* am e.e $ Yc G10 stobuftcrvs Y f vu ace._ W ung-17 g at> p su k.k +

within = 20fc of the average flow per unit when tc>ted in accord.mce with the provisions of Scetion 9 of " Industrial Ventilation" and Section 8 or .

ANSI N510-1975.

FEB i i 1977 CALVERT CLIFFS-UNIT 1 3/4 7-24 1

F

. kp .. , . . . , .

w,. r! . .-o, . * ' r~r: . -

,,;7,c,

.n-

' m. .

.. . , ~,r* ,Y g.. y

~

g , .,-.v.e" 8 t.. tp .

. if. ' n y.i

. .,e

' " 7

] REFUELING OPERATIONS FCA ~7M4-4'.

4 :s -

t . r

,".h.

• • c. .N _ z:

., .:nn. : o' m- M e.g,r _.y.

SURVEILLANCE REQUIREuENTS (Continued)

'j., -:V 4,$.l2 A d .- M [ d 5 7 4 M f C N7 M . J J-f 4 M # d d *'

At least once per 18 months by:

1. l . g #.' w

.a i Verifying that the pressure drop across the combinedIPkN

.~..

.Gauge filters while and charcoal adsorber banks is t 4. inches W

-~

9'. operating a . ..

.- rate of 32,000 cfm + 10t. the ventilation system at a flown . -<

n;

w. .t'L- f '

r.

<.. ,e . . . -

t

. y

. ~ k' 20bacross HC%rn%W ,.a x@ uw the air flow M'*M . ,

m A ' w.arcance with ANSI N510-1975. orberswhent.es;ted 3., ~

7 .: ,

fVerifying that each exhaust fan maintains tha. spent fu>el

.y. l Water Gauge relative to the outsw system operation.

' 'T

e. .

.M.. ' m'. " e r- .

- . .** T:

, . y' bank by verifying that the HEPA filter banks rem .

+

ANSI N510-1975of the DOP when they are testede in-place in accorda with

-.t

. flow rate of 32,000 cfm + 10Lwhile operating the ventilation system M. ",

f. ..

~

i

After each complete or partial replacement of a .charcoal

"~ adsorber bank by verifying that the charcoal adsorbers ('

,~

~

. Y ', .N <*7- ,

- ~ ~ ~

(

~ ' remove > 99% of a halogenated 7rM

. N510-1975 hydroc -

" rate of 32,000 '

while cfmoperating + 10%. the ventilation system at a flow 3, g ~

a.- .:

. .. t 4., c ~.1

~ .

. ~-

.-l. ~P; b(. . ... .

. . -a . , :l .

x. .

.. .,%y.,; . .-

g

..~ ,, 7. .  :

.:.. , . .m ;, . .

.;-r.. ., :q.

. . .g .

- .,. - v v.. ,.

,. c-t. .t

.. ~

. .. .

. . .o . ..

g  %. ..

.;v. m

',w. .w-<.~ . . ,:;. .

. . ..- ;..- . .a . . .,;:

- . . - +.:

'g * . .~ - .

. p . .. . -

,.p.. . .

z../. :1

.- g -

.e . ,..=-w *-e

s

. '4 .... * *

. . F l .. . .

.. . .- ... . a. -

r.h

~ . , .

r

..A ., .. .

p.s .

, . r

. ~. j. y. . y .. : :.

. . . ..s-;. Q ...

.~,.

.p, - -

y . < ?.- .-., %  %,..., .y.g ;; .s.

ci. ..

. s ca . ~ . . - . M ,, a - ,. 4 ) %. %p~

CALVERT CLIFFS ' UNIT.1 i W;:'W;g Q. . , .,

. ~gg-.;r..n

... . . -~  :.....,.. 3 W# D$

, i.p % .,:: .,:.  ;. . .. ' N-f. 24.g,

., .U  :. @P W.;n... c%M5.g n :x ,4; }me'ndment.No']

-:u ...s.G. idgir.i.

.x ..3. h ;;; Q.; ow.w*. QIff.p. g & i;.g y

• ,~ 3 ;.W. .y.. . .n. .. .;a . 2. e._ .- q.yu w . n.:. - .

.s. 5tt. -f. a QN,l m,y N!#%t 6. V.'. Qme.g, u. .E' 5-f,.Ah.W ' '+ .

/. ht J.P. "*W;W .r.3.JT.VCpw -

Fca w-w i l

REFUELING OPERATIONS l

l SURVEILLANCE REQUIREMENTS (Continued)

d. At least once per 18 months by:

1. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is < 4 inches Water Gauge while operating the ventilation system at a flow rate of 32,000 cfm i 100,

2. Verifying that fMe air flow distribution is uniform within 205. across HEPA *ilters and charcoal adsorbers when tested in accordance wi:h ANSI N510-1975.

3. Verifying that each exhaust fan maintains the spent fuel I storage pool area at a negative pressure of 1 /8 1 inches Water Gauge relative to the outside atmosphere during system operation.

e. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove 1 99's of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 32,000 cfm i 10%.

f. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove 1 99', of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI i

N510-1975 while, operating the ventilation system at a flow rate of 32,000 cfm i 101.

. kV r.t aube ce. C ' & {hnir W fg}$f" Y within = 20fc of the aversge flow per unit when tested in accordance with the provisions of Scetion 9 of " Industrial Ventilation" and Section 8 of ANSI N510- 1975 l CALVERT CLIFFS - UNIT 1 3/4 9-15 AmendmentNo.J4 l

l l

n N

y TABLE 3.7-4

--a p SAFETY RELATED HYDRAULIC SNUBBERS

• 5 Y SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE UR HIGH RADIATION ESPECIALLY DIFFICULT E NO. ON, LOCATION AND ELEVATION INALCESSIBLE ZONE **

- 10 REMOVE (A or 1) (Yes or No) (Yes or No}

1-36-1 SUCTION #11 AUX. FEED PUMP 12' A No No 1-36-1A SUCTION #11 AUX. FEED PUMP 12' A No No 1-36-3 DISCHARGE #11 AUX. FEED PUMP 12' A No No

, 1-36-3A DISCHARGE #11 AUX. FEED PUMP 12' A No No s

1-36-4 DISCHARGE #12 AUX. FEED PUMP 12' A No No S I-36-4a DISCHARGE #12 AUX. FEED PUMP 12' A No No 1-38-1 PRESSURIZER SAMPLE LINES 13' WI Yes No 1-38-2 PRESSURIZER SAMPLE LINES 13' WI Yes No 1-38-4 PRESSURIZER SAMPLE LINES g38' #I Yes No 1-38-5 g l- 36-lo PRESSURIZER SAMPLE LINES WZ4' P06S50211f4 ShMhE befS 37*

1. I T

Yes 1es No No Qg no 1-24-1 DIESEL GENERATOR #12 EXHAUST 92' A No No 5 E

l-24-2 DIESEL GENERATOR #11 EXHAUST 92' A No No

)@h

-J v

,E W' U =

U

, n g TABLE 3.7-4 G

g SAFETY RELATED HYDRAULIC SNUBBERS

• n C SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR "IGH RADIATION ESPECIAlt.Y DIFFICULT 5 NO. ON, LOCATION AND ELEVATION INACCESSIBLE ZONE ** TO REMOVE

[ (A or I) (Yes or No) (Yes or No) 2 1-52-11 S/D COOLING TO LPSI SUCTION -15' A No No

]

1-52-12 SUCTION TO HPSI PUMP #12 -15' A No rio 1-52-13 LPSI PUMP #12 DISCHARGE -15' A No No 1-52-14 LPSI HEADER -15' A flo No 1-52-15 LPSI PUMP #12 DISCHARGE -15' A flo rio 1-52-16 12A SI HEADER /25' /I X Ves rio 1-52-17 AUX. HPSI HEADER TO LOOP ilA 5' A No No 1-52-18 LETDOWN LINE - PENETRATION 34' I Yes flo 1-52-21 LPSI HEADER 5' A No No 1-52-22 LPSI HEADER 5' A No No 1

t

=

O Jm

=

m F

=a

~

n TABLE 3.7-4

?

SAFETY RELATED HYDRAULIC SNUBBERS

• b SNUBBER SYSTEM SNUBBER INSTALLED ACCES$1BLE OR HIGH RADIATION 4 NO. ON, LOCATION AND ELEVATION ESPECIALLY DIFFICULT ,

INACCESSIBLE ZONE" TO REMOVE

{ (A or 1) (Yes or lio) (Yes or flo)

A 1-52-66 SI LOOP 11A CHECK VALVE

- LEAKAGE 47' I Ye; Po i

1-52-67 SI LOOP 11A CHECK VALVE LEAKAGE 49' I Yes No 1-52-68 SI LOOP 11A CHECK VALVE LEAKAGE 49' I Yes No 1-52-69 SI LOOP 11A CHECK VALVE LEAKAGE 48' I Ves i;o

$ 1-52-70 SI LOOP.11A CHECK VALVE y LEAKAGE 47' I Yes flo A

1-52-71 SI LOOP 11A CHECK VALVE LEAKAGE 47' I Yes  !!o 1-52-72 SI LOOP 11A CHECK VALVE LEAKAGE 47' I Yes No 7J. 1-52-73 SI LOOP 11B CHECK VALVE iA

[ LEAKAGE 48' I Yes No 3

", 1-52-74 .xA HPSI HEADER TO LOOP llB 5' serAo rio -J

%v p

1-52-75 SI TO LOOP 11A 48' I Yes No $

p

bs[A(h Q fcd ~1!r li2-

.u w

ww -

~~ > C og =s.

>. w

.,J, K O.

<o e e

-- o u >-

=

w

• C m

w

=

o

~

~

s

<.e 2 4 L I Cw O

<=

2C m N a

N O

= >-w u

=_.

(. m a

w e e 1 e Cw'

= -

= we_. -

m a-u em s.

-m o H w - mw

. a

= mu<

wv -

~. < vc M c v=

w a.

a m

= .

< e

& w w

W e

m '

CC w

w-a-

a""

w a< m

< <> s v WW Q ma

=w >-

( 'e E-

=z c- to M*

cz ^6 w

o

=- w%'

m- g

-x x <v -s wo

>J

<=

e--

m =c

>- - os mz vm C

= e w

e . .

me -

==

= e.

m .. -

CALVERT CLIFFS-UNIT 1 ,

~/4 7 O emenhent No. 25 P

.n TABLE 3.7-4

?

F, SAFETY RELATED HYDRAULIC SNUBBERS

• 4 h SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION 4 NO. ON, LOCATION AND ELEVATION INACCESSIBLE 70NE**

ESPECIALLY DIFFICULT

', TO REMOVE E (A or I) _(Yes or No) (Yes or No) q 1-64-98 RCP 11A and llB MOTORS 56' I Yes No 1-64-99 RCP llA and 118 MOTORS 56' I Yes No 1-64-100 RCP 12A and 128 MOTORS 56' I Yes No 1-64-101 RCP 12A and 128 MOTORS 56' I Yes No 1-64-102 RCP 12A and 128 MOTORS 56' I Yes No 1-64-103 RCP 12A and 12B MOTORS 56' I Yes No

$ l-67-1 #11 SPENT FUEL POOL C00L.

y PUMP SUCTION - RWT 27' #A M MO No 1-67-2 INLET - SPENT FUEL POOL COOLER #12 27' #A X Mo No 1-67-2A INLET - SPENT FUEL POOL COOLER #12 27'

1. A JefNO Ho 1-6"-3 WATER TO REFUELING P00L #11 38' I Yes No g

,@ 1-67-4 WATER TO REFUELING e

s

,. e00t nii 40- I Yes No g

p2

=

9 g , TABLE 3.7-4 Si g SAFETY RELATED HYDRAULIC SNUBBERS

• P q SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION y NO. ON, LOCATION AND ELEVATION ESPECIALLY DIFFICULT INACCESSIBLE ZONE ** TO REMOVE

& (A or I) (Yes or No) z (Yes or No)

U 1-69-1 AUX. STEAM SUPPLY TO WASTE M

EVAPORATORS 33' MMO No 1-71-1 DESUPERHEATED STEAM TO WASTE EVAPORATORS 83' A No rio 1-71-2 MISC. WASTE EVAP. STEAM SUPPLY 69' A No tio 1-71-2A MISC. WASTE EVAP. STEAM SUPPLY 69' A No No 1-71-3 LETDOWN H/X RELIEF TO RC y WASTE RECEIVER TANK #12 40' A No Yes

-E l-71-4 DRAINS TO RC DRAIN TANK #11 24' I Yes fio 1-83-1 MAIN STEAM FROM S.G. #11 27' A No Yes 1-83-2 MAIN STEAM FROM S G. #11 27' A No . ;s 1-83-3 1-83-4 MAIN STEAM FROM S.G. #12 27' MAIN STEAM FROM S.G. #12 27' A No Yes h

n A No No 5, 7 N

as w

$ b b v

~

TABLE 3.6-1 (Cont.)

=} CONTAINMENT ISOLATION VALVES 4

P PENETRATION ISOLATION VALVE ISOLATI0ft 2

m NO. IDENTIFICATION NO. FUNCTION TIME (SEC0!!DS)

., c: 208 223-1 Nitrogen Supply flA

} 223-2 flA N"

20C 223-1 Nitrogen Supply NA 223-2 NA 23 CV-4260 R.C. Drain Tank Drains 17

, 24 SV-6531 0xygen Sample Line 17

~

1

'? 37 29-1 Plant Water NA U ,

142-1 NA '

38 CV-5460

• Demineralized Water NA

, A * %.m a W

6 39 ( 130M3-1 ~2- Safety Injection Tank Test Line NA

-w.) a. - .

130M3-2 -J.' NA

~

3 "~ 41 MOV-652(2) Shutdown Cooling NA v j% MOV-651 (2) NA ^

s e l L o)) m;% &

.j.

TABLE 3.6-1 (Cont.)

9 CONTAINMENT ISOLATION VALVES

G ,

9 i

PENETRATION ISOLATION VALVE ISOLATION P NO. IDENTIFICATION NO. FUNCTION TlHE (SECONDS)

9 3 i;A

. 61 76Y-1 Refueling Pool Outlet c 293H-1 kA 5 293M-1 NA

. 293M-1 NA f"

62 MOV-6579 Containment Heating Outlet 113 M

238-1 Containment Heating Inlet NA

-[

64 h

(1) Manual or remote manual valve which is closed during plant operation.

i (2) May be opened below 300*F to establish shutdown cooling flow, D

4

• May be open on an intennittent basis under administrative control.

• B s

h,v

~

c f, 4l $

m D ,

j 2.2.2 Treatment Chemicals W J2. h .

j

{ ]h'-l bI i Objective To identify and quantify significant treatment chemicalc used in the plant.

Specification This specificatien applies te treatment chemicals added or used in .significant quantitles in the plant.

The total amounts of the below listed chemicals' added or used in the plant tk EAdicomMT.11 shall be reported in-s-6emiwAnnual operating Report.

1. Phosphates

2. Boric Acid 3 Hydracine

/

h. Sodium Hypochlcrite Monitorina Fenuire.?ent A rete -i shall be kept of the chemical store receipts and use of sodium, phosphate, boric acid, hydracine and hypochlorite.

Basis Sodium phosphate =ay be used in stea= generators at concentrations that range frem 30 to 60 ppm. The steam generator blevdown rate is expected to be en the average 2 GPM, and the phosphate concentration in the blevdown is not expected to exceed 60 ppm. The blevdevn shall be mixed with the circulating vater flcving s

at a rate no less than 15,500 GPM per conduit. The calculated chance in the cencentratien of phosphate in the final discharge vill not exceed 0.009 pps and vill be within the natural variation of the phosphate concentratiens ob-served during 1969 through 1971 in the plant intake and discharge areas.

In crder to control reactivity within the reacter coolant during reseter cperation, boric acid is used ss a chemieni shim in the reaeter coolant at a concentratice of about 800 ppm. The reactor coolant is periodically processed for radicactive decentamination which is accomplished by several treatment precesses including evaporation. The evaporators used for this purpose are expected to yield a distillate with boren concentration not to exceed 10 pps.

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REFUELING OPERATIONS REFUELING MACHINE OPERABILITY LIMITING CONDITION FOR OPERATION 3.9.6 The refueling machine shall be used for movement of CEAs or fuel assemblies and shall be OPERABLE with:

a. A minimum capacity of 1550 pounds, and

b. An overload cut off limit of < 3000 pounds.

APPLICABILITY: During movement of CEAs or fuel assemblies within the reactor pressure vessel.

ACTION:

With the requirements for refueling machine OPERABILITY not satisfied, suspend its use from operations involving the movement of CEAs and fuel assemblies within the reactor pressure vessel. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS , 4.9.6 The refueling machine shall be demonstrated OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of movement of CEAs or fuel assemblies within g h the reactor pressure vessel by performing a load test of :t h;;t '::C pg5 ~

f.ewedt and demonstrating an automatic load cut off when the crane load exceeds 3000 pounds:

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3. - anm Ganar. a r I;erar tevn1 Risa nata Except the pur,cca of performing ste:m genere feedwater f L stability tosts, tne licensee all, whenever the se d ary side water level a steam generator is M1ow level of rne .edwater sparger, limit tne secondary side ,ter .el~ rise rate in tne steam generator to less th 2 inches per minute and shall reduen the rise - to u '

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4. IA3 Traffic at Cova Point Tarninal The licensee shall provide one of tne following items to the Comission 60 days prior to the initiation of m3 ship

-traffic at the Cove Point IBG Receiving Teminal:

a. An analysis to show that the probability of an accident that could affect plant safety due to an ING tanker approaching closer to the plant than the distances assumed in the safety analyses (discussed in Su,olement No. 5 to the Safety Evaluation Report) is acceptably small, as defined in Section 2.2.3 of trJREG-75/037; or

b. A com itment from the appropriate U. S. Coast Guard Port Authority that administrative limits will be imposed to prevent m3 traffic from approaching Calvert C1iffs Nuclear Plant closer than the distances assumed in the above-referenced analyses.

In addition, the licensee shall establish a mechanism-whereby it will ' oe promptly notified oy the U. S. Coast Guard of abnormally dangerous occurrences involving m3 traffic in tne vicinity of the Cove Point MG Receiving Terminal.

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